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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 ML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration 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 ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld 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 ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program 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 ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) 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 ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. 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 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 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 ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety 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 ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity 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 ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS 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 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 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 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 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 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 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 ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided 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 HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 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 ML20246N1281989-02-27027 February 1989 FOIA Request for Jl Smith to NRC Re Spent Fuel Shipment from Brunswick Nuclear Power Station to Harris Plant 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 ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls 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 ML20234B6211987-05-12012 May 1987 Requests That Listed Plants Be Added to Encl 870508 FOIA Request Re 94300 Region Input on Plant Readiness 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 ML18004B8351987-03-27027 March 1987 Forwards EGG-NTA-7492, Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Shearon Harris Nuclear Power Plant,Unit 1, Final Rept.Proposed Program in Accordance W/ NRC Regulations,W/Exceptions Noted in Rept 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 ML18018B7451984-06-25025 June 1984 Forwards NRC Staff Exhibits 1-3 & Intervenor Exhibit 1. Related Correspondence 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 ML20083N5521983-02-0808 February 1983 Forwards Draft Technical Evaluation Rept,Per Contract NRC-03-82-118 ML20083N5411982-09-23023 September 1982 Forwards Draft Hydrologic Engineering Summary for Inclusion in Draft Ser.Several Open Items & Unresolved Issues Remain 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 ML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration 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 ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) 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 ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. 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 ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety 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 ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS 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 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 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 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 ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided 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 HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 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 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 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 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 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 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 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 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 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP 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 1999-09-08
[Table view] |
Text
.. . -. _ - -. .. - .- - _ . . . .
EBASCO S imVI C E S I N 0 il it l' O H 11 E Il i UTILITY C O N S ti LT A !J T S - E N GIN E E R S - CONSTRUCTORS TWO Ill.CT OR SIRI:LT N LW YOHH, N.Y.10006 CABLR ADDRE&S "ESASCON" November 9, 1978
, Mr. Walter P. Ilaass, Chief Quality Assurance Branch Division of Project Management ;
U S Nuclear Regulatory Commission i Washington, D. C. 20555 l
Dear Mr. Haass:
This is to acknowledge receipt and thank you for your letter of October 5,1978 to [
our Mr. L F C Reichle accepting recently proposed revisions to Ebasco Topical Report No. ETR-1001, "Ebasco Nuclear Quality Assurance Program Manual'.' The revisions are being included in the Topical Report. j In accordance with your request, thirty-five (35) copies of the revised or new sec-tions (initial page only on the case of Section QA-I-1), each including updated 3 Table of Contents, the Nuclear Regulatory Commission letter of acceptance of October '
5, 1978 .and transmittal memorandum for the package, are transmitted.
The following of our existing contracts will be covered by Change 6 to ETR-1001:
Carolina Power & Light Co. Shearon Harris Nuclear Power Station Units 1,2,3,6 4 Houston Lighting & Power Company Allens Creek Nuclear Power Station Unit 1 Louisiana Power & Light Company Waterford Steam Electric Station Unit 3 l
Washington Public Power Supply System Nuclear Projects 3 and 5 Since Preliminary Safety Analysis Reports for all of the above contracts were dock-eted prior to October 19, 1977, the exceptions stated in Sections QA-III-13, Revision 2, paragraph 3.2, page 2 of 2, and in the EBASCO POSITION under REGULATORY CUIDE 1.94 in APPENDIX 11, Revision 0, page 3 of 4, apply.
Very truly yours, BET /mc B E Tenzer Attachments Director, Materials Engineering cci F Liederbach and Quality Assurance C J Hale, NRC Region IV, 0.I.& E B R Mazo O .h k
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TO: Assignee of Ebasco Nuclear Quality Assurance Program Manual No.
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FROM: F F Ford, Quality Program Coordinator'
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SUBJECT:
EBASCO NUCLEAR QUALITY ASSURANCE PROGRAM MANUAL (ETR-1001)
Table of Contents, Revision 6 of 10/20/78 l Section QA-I-1, Revision 4 of 10/20/78 l Section QA-III-13, Revision 2 of 10/20/78 APPENDIX II, Revision 0 of 10/20/78 One copy each of the below listed revised pages are transmitted for insertion in your copy of the Ebasco Nuclear Quality Assurance Program Manual (in blue binder).
Superseded pages are to be destroyed.
Table of Contents, Revision 6, pages 1 and 2 of 2. These replace existing Table of Contents, Revision 5 pages of the same number.
Section QA-I-1, Revision 4, QUALITY ASSURANCE PROGRAM, page 1 of 12. This replaces existing Section QA-I-1, Revision 3, page 1 of 12. Note that un-revised pages of this section are not included in this transmittal and therefore should not be discarded from your manual.
O)
( Section QA-III-13, Revision 2, CONTROL OF MEASURING AND TESTING EQUIPMENT, pages 1 and 2 of 2. These replace existing Section QA-III-13, Revision 1 pages of the same number.
APPENDIX II, Revision 0, EBASCO POSITIONS ON US NUCLEAR REGULATORY COM-MISSION REGULATORY GUIDES, pages 1 thru 4 of 4. These are new pages to be inserted at the rear of the manual af ter APPENDIX I.
NRC (Walter P. Haass) letter dated October 5, 1978 tc L F C Reichle ac-cepting the revisions. This is for insertion in the front of the manual behind the original NRC letter of acceptance dated May 12, 1975, and re-places NRC letter of acceptance dated July 26, 1977 pertaining to change No. 5.
An index tab divider sheet for new Appendix II is included for insertion in the back part of your manual behind Appendix 1, and ahead of Updating Status Memos, in the event an Appendix II index tab is not already in place.
FFF/mc Attachments:
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6109 6/2 75 PAGE I OF ESA5CO SERVICE 5 HUCLEAR QUALITY ASSURANCE PROGRAM MANUAL SECTION INCORPORATED g.
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c a... M,..g.L os . , , os TABLE OF CONTENTS nevision 6 ']
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Part I - General Section Title- Rev. No. Date QA-I-l Quality Assurance Program 4 10/20/78 R6 QA-I-2 Organization and Responsibilities- 2 9/30/76 QA-I-3 Personnel Indoctrination and Training 2 8/11/77 Program in Quality Assurance
-QA-I-4 Design Control 1 8/11/77 QA-I-5 Quality Assurance Evaluation of 1 9/30/76 l Supplier / Contractors QA-I-6 Quality Assurance Records 0 3/14/75 Part II - Engineering Offices j
Section Title Rev. No. Date l
1 QA-II-1 Instructions, Procedures and Drawings 1 9/30/76 l QA-II-2 Document Control 1 9/30/76 l
QA-II-3 Procurement Document Control 0 3/14/75
-QA-II-4 Purchasing 1 4/16/76 QA-II-5 Supplier Surveillance 1 8/11/77 QA-II-6 Nonconformances 1 8/11/77 QA-II-7 Corrective Action 0 3/14/75 QA-II-8 Control of Special Processes 0 3/14/75 QA-II-9 Quality Assurance Audits I 11/16/76 O
d
_ _ _ _ ._ __ _ . . . . _ _ - _ _ ~ _
6 61094A/2 74 PAGE 2 OF 7 HLlCLEAR QUALITY A550RANCE PROGRAM MANUAL SECTiow O ESASCO SERVICES mcomponave TABLE OF CONTENTS Part III - Construction Site Section Title Rev. No. Date QA-III-1 Instructions, Procedures and 1 4/16/76 Drawings QA-III Document Control 1 4/16/76 QA-III-3 Procurement Control 0 3/14/75 QA-III-4 Construction Site Procurements 3 8/11/77
-QA-III-5 Supplier,' Contractor Surveillance 2 8/11/77 QA-III-6 Nonconformances 1 9/30/76 QA-III-7 Corrective Action 1 8/11/77 QA-III-8 Control of Special Processes 0 3/14/75 QA-III-9 Quality Assurance Audits 0 3/14/75 QA-III-10 Identification and control of Items 0 3/14/75 QA-III-11 Inspection 1 8/11/77 ,
QA-III-12 Test Control 0 3/14/75 QA-III-13 Control of Measuring and Testing 2 10/20/78 R6 Equipment QA-III-14 Control of Receiving, Handling and 1 4/16/76 Storage QA-III-15 Inspection, Test and Operating Status 0 3/14/75 Appendix I Terms and Definitions 1 9/30/76 Appendix II Ebasco Positions on U.S. Nuclear Regulatory Commission Regulatory Guides 0 10/20/78 R6 O ;
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PACE 1 or 17 NUCLEAR QUALITY ASSURANCE PROGRAM MANUAL SECTION tBA5CO 5ERVICES IN CoR PoR AT E D AA T_1 A4 RE VISION 4
- a6, esopau touw, twainuam DATE -10/20/78
$ c ,.. . , <p, . n a u c ........ QUALITY ASSURANCE PROGRAM 1.0 SCOPE The purpose of this section is to describe the Quality Assurance Program of Ebasco Services Incorporated and its applicability to safety-related activities.and ser-vices performed by Ebasco in the design and construction of nuclear power stations.
This Program has been designed to meet the requirements of the United States Nuclear
~
Regulatory Commisrion 18 Quality Assurance Criteria of 10CFR50, Appendix B. It has ,
also been designed to meet the regulatory position of the following US NRC Regulatory .
Guides and ANSI Standards, with exceptions and clarifications as stat'ed inAppende'x II of8' this manual:
- 1. Reg. Guide 1.28 Rev. O,(6-72) 8. Reg. Guide 1.70 (Chap.17) Rev.2 (9-75) ,
- 2. " "
1.30 "
0 (8-72) 9. " "
1.74 Rev.0 (2-74) ,
- 3. " "
1.37 "
O (3-73) 10.
" " 1.88 2 (10-76) R4 l
- 4. " "
1.38 "
2 (5-77) 11.
1.94 1 (4-76) '
l
- 5. " "
1.39 " 2 (9-77) 12.
1.116 OR(5-77) l
- 6. " "
1.58 " b (8-73) 13. " "
1.123 1 (7-77) '
l
" " " 14. Standard N45.2.12, i
- 7. 1.64 2 (6-76 ) " ' '
. Draft 3, 4 (2-74)
\
[m4able I-1.1 provides a matrix wh,1ch shows the sections of the Ebasco Nuclear Quality l Assurance Program Manual that correspond to the requirements of 10CFR50, Appendix 1 R4 B and US NRC Regulatory Guide 1.28, Rev. O. The Ebasco Qual,ity Assurance Program l' 1s comprised of: The Ebasco Nuclear Quality Assurance Program Manual, written corporate policies, procedures, departmental instructions, and drawings related to l' quality. Table'I-1.2 provides a matrix of the principal implementing procedures with 10CFR50, Appendix B. Table I-1.3 is a listing of these procedures by citle.
The Ebasco Nuclear Quality Assurance Program Manual has been designed to meet the requirements of 10CFR50.34 (7) for a quality assurance program description. It will be incorporated into applicable portions of safety analysis reports by reference as provided by 10CFR50.32*.
The Ebasco Quality Program is in force at Ebasco Engineering Offices and Construction Operat ions. Ebasco Engineering Offices are those district organized units where design, engineering, procurement and related functions are performed. Construction Operations encompass those activities related to the construction of a nuclear power station. Ebasco's responsibility for.. implementing the Ebasco Quality Program shall begin at'the commencement of activities affecting quality and shall end with the turn-over of completed systems to the Client.
Definitions pertaining to the Ebasco Quality Program are listed in Appendix I of this manual.
2.0 QUALITY ASSURANCE FYCINEERING 2.1 The Ebasco Quality Assurance Engineering Department is responsible for p
establisning new, and updating existing quality assurance requirements. In addition, this department is responsible to administer and enforce the implemen-tation of the Ebasco Quality Assurance Manual.
6109 4/2 75 PAGE I OF 2 ;
EB A5CO SERVICE 5 NUCLEAR QUALITY ASSURANCE PROGRAM MANUAL SECTION INCoRPoAATED OA-III-13 i O. ,g J.sg[ CONTROL OF MEASURING ,
2 g 2.. ... 6 . . . . . . . < AND TESTING EQUIPMENT ae vision I. _
omic 10/20/78 1.0 SCOPE 1.1 This section describes the requirements for control, calibration, adjustment and maintenance of measuring and testing devices used at the construction site for performing tests and inspections of safety-related items. These devices shall be calibrated and adjusted at specified,. predetermined intervals using equipment having known valid relationships to nationally recognized standards.
1.2 The activities described herein shall be performed in accordance with written instructions, procedures, and/or drawings that have been developed and accepted in accordance with the requirements of Section QA-III-l of this Manual.
2.0 RESPONSIBILITIES The Site Quality Control Staff shall be. responsible for performance of the following: -
2.1 Establish a list which includes the measuring and testing devices O- to be calibrated and the frequency of calibration of these devices.
The method and interval of calibration shall be based on the type of device, stability characteristics, required accuracy and other conditions affecting measurement control..
2.2 Assure that the measuring and testing devices used are of the proper range, type and accuracy to verify conformance to established requirements.
2.3 Maintain a master calibration file for each measuring and testing device which includes at least the following information:
(a) name of device (b) device serial and/or identification number (c) frequency of calibration (d) date of last calibration (e) name of party performing last calibration (f) due date for next calibration 2.4 Assure that all measuring and testing devices are marked with calibration due dates when possible. When this marking is not possible, alternative methods of tracing the device to its calibration date (such as serialization) shall be employed.
2,5 Assure that all measuring and testing devices are calibrated in accordance. with the requirements of this section and that the required
\~ documentation is provided.
PAGE 2 o, 2 81094 A/2 75 NUCLEAR QUALITY ASSURANCE PROGP.AM MANUAL SECTION
/ EBASCO SERVICES CONTROL OF MEASURING QA-III-13
("7/ mcomponarro AND TESTING EQUIPMENT 2.6 Develop and maintain a system for issuance, collection and return of all measuring and testing devices. This system shall provide for the identification of personnel withdrawing devices, methods for issuing devices and methods for the collection and/or return of devices at prescribed calibration times or as othetvise required.
3.0 GENERAL 3.1 The standard of calibration utilized by those performing the calibration shall be in accordance with recognized criteria such as Departments of Weights and Measures, ASTM standards or others which are traceable to the National Bureau of Standards. If no national standards exist, the basis for calibration shall be documented.
3.2 Measuring and Test Equipment (M&TE) shall be calibrated against working '
standards having tolerances not greater than one fourth (k) the tolerance '
of the M&TE. Tolerances greater than one fourth (k) shall be acceptable '
when limited by the state of the art. Reference standards shall be calibrated against higher level standards of closer tolerance. R2 For projects with Preliminary Safety Analysis Reports docketed on or before '
O October 19, 1977, M&TE shall be calibrated against working standards V having tolerances not greater than the tolerance of the M&TE. Reference '
standards shall be calibrated against higher level standards of closer ' l tolerance.
3.3 Methods shall be employed to assure proper handling, storage and care of the M 6 T E in order to maintain its required accuracy. R2 3.4 Any M & T E found to be out of calibration shall be recalibrated. R2 When M & T E is found to be out of calibration, an evaluation shall R2 be made to ascertain the validity of previous inspection or test results and the acceptability of components inspected and/or tested since the last calibration check. When it is necessary to assure the acceptability of suspect items, the original required inspections and/or tests shall be repeated using properly calibrated eauipment.
3.5 If any of the M & T E is consistently found to be R2 out of calibration, it shall be repaired or replaced.
3.6 Inspection and test reports shall include identification of M & T E R2 used to perform the inspections and/or tests.
3.7 The Quality Assurance Site Supervisor shall be responsible for the performance of reviews and audits in accordance with Section QA-III-9 of the Manual to the extent necessary to assure compliance with the
/ requirements of this Section.
4.0 RECORDS 4.1~ Records pertaining to this section shall be maintained in accordance with Section QA-I-6 of this manual.
sios4n.7s pace 1 or 4
. EBA5CO $ERVICES - HUCLEAR QUALITY ASSURANCE PROGRAM MANUAL $5cTioH INCoRPORATeo.
l i EBASCO POSITION 9 ON US NUCLEAR g
[c ... ...g7.. MIc.oo. REGULATORY COMMISSION REGULATORY GUIDES Ae Vi$lON O l l pare 10/20/78 4 c.ap n. .. ..c .. .
e q REGULATORY GUIDE 1.28 QUALITY ASSURANCE PROGRAM REQUIREMENTS (DESIGN AND l CONSTRUCTION) (SAFETY GUIDE 28, REVISION 0, 6/72)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to'the guide.
REGULATORY GUIDE 1.30 QUALITY ASSURANCE REQUIREMENTS FOR THE INSTALLATION, 4 INSPECTION, AND TESTING OF INSTRUMENTATION AND i ELECTRIC EQUIPMENT (SAFETY GUIDE 30, REVISION 0, 8/72)
EBASCO POSITION a Ebasco commits to comply with the regulatory position as written with no exceptions
- or clarifications to the guide.
l i REGUALTORY CUIDE 1.37 QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF
' 1 FLUID SYSTEMS AND ASSOCIATED COMPONENTS OF WATER-() ERASCO POSITION COOLED NUCLEAR POWER PLANTS (REVISION 0, 3/73)
Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide.
REGUALTORY GUIDE 1.38 QUALITY ASSURANCE REQUIREMENTS FOR PACKAGING, SHIPPING, STORAGE AND HANDLING OF ITEMS FOR
' WATER-COOLED NUCLEAR POWER PLANTS (REVISION 2, 5/77)
EBASCO POSITION l
Ebasco commits to comply with the regulatory position with the following clarifica-tions:
1 CLARIFICATION Item-ANSI N 45.2.2-1972 Ebasco believes the intent of the ANSI Subdivision 2.7 classification of protection levels is met if equipment identified in Level B and C categories which was specifically designed for outdoor environment is stored at Level D (outdoor) conditions.
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sios4a/2 7s paos ? or 4 NUCLEAR QUALITY AS$URANCE PROGRAM MANUAL SECTION '
g,,) E8A5CO SERVICE 5 EBASCO POSITIONS ON US NUCLEAR REGULATORY COMMISSION REGULATORY GUIDES APPENDIX II REGULATORY GUIDE 1.38-(cont.)
Regulatory Position Ebasco believes that storage conditions should be such C.1.c and C.2.c that desiccants, their bags and tapes should not be sub-jected to leaching or radiation. Even if accidental leaching or radiation occurs, desiccants and tapes are removed prior to component installation. Subsequent routine flushing and/or cleaning would remove any harmful residues.
Ebasco will impose the more readily interpretable require-ments of 0.25% maximum halogens for desiccants (c.1.c) and 0.10% halogen and sulfur content for tape (C.2.c)
REGULATORY GUIDE 1.39 HOUSEKEEPING REQUIREMENTS FOR WATER-COOLED NUCLEAR POWER PLANTS (REVISION 2, 9/77)
EBASCO POSITION Ebasco commits to comply with the regulatory position . ;a the following clarifica-O tion:
CLARIFICATION Item-General Ebasco acceptance applies only to the regulatory require-ments for controls at the site during the construction phase and not to the operational aspects of this guide or the referenced documents.
REGULATORY GUIDE 1.58 QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION, EXAMINATION, AND TESTING PERSONNEL (REVISION 0, 8/73)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide.
REGULATORY GUIDE 1.64 QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS (REVISION 2, 6/76)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide.
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slossA/27s PAos 9 or 4 HUCLEAR QUALITY AS$URANCE PROGRAM MANUAL SECTION EBA5CO SERVICE 5 EBASCO POSITIONS ON US NUCLEAR REGULATORY mcomponareo APPENDIX II COMMISSION REGULATORY GUIDES REGULATORY GUIDE 1.70 STANDARD FORMAT AND CONTENT OF SAFETY ANALYSIS (Chapter 17) REPORTS FOR NUCLEAR POWER PLANTS (REVISION 2, 9/75)
EBASCO POSITION The Quality Assurance Program and its applicability to safety related activities and services performed by Ebasco in the design and construction of nuclear power plants is fully delineated in this topical report (ETR-1001).
REGULATORY GUIDE 1.74 QUALITY ASSURANCE TERMS AND DEFINITIONS (REVISION 0, 2/74)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide.
REGULATORY CUIDE 1.88 COLLECTION, STORAGE, AND MAINTENANCE OF NUCLEAR O
\ POWER PLANT QUALITY ASSURANCE RECORDS (REVISIONS 2, 10/76)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide.
REGULATORY GUIDE 1.94 QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION, INSPECTION AND TESTING OF STRUCTURAL CONCRETE AND STRUCTURAL STEEL DURING THE CONSTRUCTION PRASE OF NUCLEAR POWER PLANTS (REVISION 1, 4/76)
EBASCO POSITION Ebasco commits to comply with the regulatory position as written, with no exceptions or clarifications to the guide for projects with Preliminary Safety Analysis Reports docketed on or after October 19, 1977. For prior projects Ebasco will comply with the applicable Safety Analysis Report and other associated commitments as approved by the NRC.
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1 stoo4A/a 7s ,, g y g y NUCLEAR QUALITY A$$URANCE PROGRAM MANUAL SECTION Es 5Co 5ERvlCES EBASCO POSITIONS ON US NUCLEAR REGUAI. TORY ]
eopp, ,,g9 APPENDIX II COMMISSION REGUALTORY GUIDES REGULATORY GUIDE 1.116 QUALITY ASSURANCE REQUIREMENTS FOR INSTALL-ATION,' INSPECTION, AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS (REVISION 0-R, 5/77)
EBASCO POSITION Ebasco commits to comply with the regulatory position with no exceptf ons or clarifi-cations to the guide.
REGULATORY GUIDE 1.123 QUALITY ASSURANCE REQUIREMENTS FOR CONTROL OF PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER PLANTS (REVISION 1, 7/77)
EBASCO POSITION Ebasco commits, to comply with the regulatory position with no exceptions or clarifi-cations to the guide.
ANSI N45.2.12 REQUIREMENTS FOR AUDITING OF QUALITY ASSUR-
/ . .ANCE PROGRAMS FOR " LEAR POWER PLANTS (DRAFT 3, REVISION 4, 2/74)
EBASCO POSITION i
As presently written, EBASCO commits to comply with this standard with no exceptions of clarifications.
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f %,+g UNITED STATES pi >
NUCLEAR REGULATORY COMMISslON g g W ASHINGTON, D. C. 20565 V s gv j
/ OCT 5 1978 Mr. Leonard F. C. Reichle Vice-President -
Ebasco Services. Incorporated Two Rector Street New York, New York 10006
Dear Mr. Reichle:
SUBJECT:
NRC ACCEPTANCE OF REVISION T0 QA TOPICAL REPORT By letters datcd February 13, 1978 and September 11, 1978, you submitted Revision 6, consisting of revised pages, to the Ebasco Topical Report No. ETR-1001. The revisions concern clarification of scope and comit-ments to certain NRC Regulatory Guides.
We have evaluated the proposed revisions and have found that they do not change our prior conclusions. Your revised topical report meets the criteria of Appendix B to 10 CFR Part 50 and is therefore acceptable.
To use the topical report in license applications, applicants need only reference this topical report in Section 17 of the Safety Analysis Report.
We do not intend to repeat our review of this topical report when it is A referenced in an application. In addition, the provisions of this topical V report revision may be implemented inuediately on all ongoing activities within the contractual restraints of existing contracts for nuclear power plants. In this regard, identify in your transmittal letter those existing contracts that will be covered by Revision 6 to ETR-1001.
Should regulatory criteria or regulations change such that our conclusions about this topical report are invalidated, we will notify you. You will be given the opportunity to revise and resubmit it should you so desire.
Programttic changes by Ebasco to this topical report are to be submittect to the NRC for review prior to implementation. Organizational changes are to be submitted no later than 30 days after announcement.
Please replace our letter of July 26, 1977 shown in your topical report with this letter and submit 35 copies to the NRC.
Should you have any questions regarding our review or if we can provide assistance, please feel free to contact me or Mr. Fred Liederbach on (301) 492-7741.
Sincer ly.
- W Walter P. Haass, Chief
/3 Quality Assurance Branch
() Division of Project Management
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