ML18052B191: Difference between revisions
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CALVERT CLIFFS-1 AND -2, MILLSTONE-2, AND PALISADES, 11 EGG-NTA-7720, JUNE 1987 (FINS D6001 AND D.600*2) -EWR-148-87 . | ** S-O*Jl1 311' 33, | ||
-:I.Sf" Idaho National Englnflflrlng Laboratwy June 17, 1987 Mr. M. Carrington, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 TRANSMITTAL OF FINAL REPORT, 11 CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28, REACTOR TRIP SYSTEM VENDOR INTERFACE: CALVERT CLIFFS-1 AND -2, MILLSTONE-2, AND PALISADES, 11 EGG-NTA-7720, JUNE 1987 (FINS D6001 AND ..--D.600*2) - EWR-148-87 . | |||
*Ref: NRC Form 189, 11 Evaluation of Conformance to Generic Letter 83-28 For ORs (Project 2) 11 (D6001); 11 Evaluation of Conformance to Generic Letter 83-28 For OLs (Project 3) 11 (D6002) | |||
==Dear Mr. Carrington:== | ==Dear Mr. Carrington:== | ||
Transmitted herewith is the above subject report. The report documents INEL's evaluation of the licensee/applicant actions in response to NRC Generic LetteF 83-28, Item 2.1 (Part 2), Reactor Trip System Vendor Interface. | Transmitted herewith is the above subject report. | ||
Based on the licensee/applicant submittals, we. conclude that the plants reviewed conform to the generic letter on this item. FGF:gp | The report documents INEL's evaluation of the licensee/applicant actions in response to NRC Generic LetteF 83-28, Item 2.1 (Part 2), Reactor Trip System Vendor Interface. Based on the licensee/applicant submittals, we. | ||
conclude that the plants reviewed conform to the generic letter on this item. | |||
E. W. Roberts, Manager NRC Headquarters Support FGF:gp | |||
==Enclosure:== | ==Enclosure:== | ||
As Stated cc: G. L. Jones, DOE-ID D. Lasher, SICB . . _ | As Stated cc: G. L. Jones, DOE-ID D. Lasher, SICB . . _ | ||
J. 0. Zane, EG&G Idaho, Inc. (w/o Encl.) | |||
( | |||
8707170226 870617 PDR ADOCK 05000255 11 | |||
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PDR | |||
. -----. --* *-*t' | |||
(::o~ EBt:G ldahO, Inc. 11428 Rockville Pike Suite 410' ; Rockville, MD 20852}} | |||
Latest revision as of 13:14, 3 February 2020
| ML18052B191 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Calvert Cliffs, Palisades, 05000000 |
| Issue date: | 06/17/1987 |
| From: | Roberts E EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | Carrington M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18052B192 | List: |
| References | |
| CON-FIN-D-6001, CON-FIN-D-6002 EWR-148-87, GL-83-28, NUDOCS 8707170226 | |
| Download: ML18052B191 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999
[Table view]Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene ML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal 1999-09-30 Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC MONTHYEARML19327A8691989-09-0707 September 1989
[Table view]Submits Info Re Alchemie & Anderson County Bank Financing Transaction ML19332F2171989-07-10010 July 1989 FOIA Request for Documents Re Communications Between Ofcs of Edo,Deputy Edo,Ofc of Director,Regional Administrators & Commissioners Ofcs Re Plants During period,890301-0615 ML20246F1311989-06-26026 June 1989 FOIA Request for Minutes of Meeting Ref in 820210 Memo from NRR Re Design & Const Assurance for Upcoming OL Cases ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20245C1421989-04-0303 April 1989 Forwards Endorsements 75,108,108,96 & 110 to Maelu Policies MF-56,MF-26,MF-58,MF-39 & MF-52,respectively & Endorsements 93,129,127,109 & 122 to Nelia Policies NF-186,NF-76,NF-188, NF-151 & NF-173,respectively ML20247N1551989-03-31031 March 1989 Forwards Revised Proprietary Conformance of HPCS Div to NUMARC 87-00 Alternate AC Criteria, for Review as Result of Comments from 890216 Meeting.Rept Withheld ML20246M7331989-03-15015 March 1989 Responds to NRC Info Notice 88-082, Torus Shells W/ Corrosion & Degraded Coatings in BWR Containments. Summary of Relevant Projects for Various Utils Successfully Employing Underwater Alternative to Draining Vessel Encl ML20246N1281989-02-27027 February 1989 FOIA Request for Jl Smith to NRC Re Spent Fuel Shipment from Brunswick Nuclear Power Station to Harris Plant ML17285A2351989-02-0606 February 1989 Forwards Proprietary Draft Conformance of HPCS Div to NUMARC 87-00 App B Aac Criteria, for 890214 Meeting ML17285A2341989-01-0606 January 1989 Discusses Issues Highlighted at BWR/6 Alternate Ac Task Force Meeting on 881115,including Need for Capability of Div III Sys to Maintain Plant in Safe Shutdown Condition (Hot Shutdown) for Min of 4 H ML20206H0511988-11-14014 November 1988 Urges Relicensing of Pilgrim & Expedited Operation of Seabrook.Newspaper Clipping Encl ML20150D5721988-03-0808 March 1988 Provides Summary of Utils Test Results & Calculations on Emergency Diesel Generators,Including Review of Design of Static Exciter & Voltage Regulator for Emergency Diesel Generators ML20196C1591988-02-0303 February 1988 Forwards Monthly Progress Rept P-C6177-5, Independent Analysis & Assessment, for Period Ending 880131 ML20147G0741988-01-18018 January 1988 FOIA Request for All Documents Re NRC Investigation of Wg Dick Allegations About S&W & Lilco Re Performing NRC Instructions to Bring Facility Up to Fuel Load Stds 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 ML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20236S4291987-10-20020 October 1987 FOIA Request for Listed Documents,Including Encls from NRC Requesting Addl Info on Gpu Topical Repts TR-033 & TR-040 & Encl to NRC Meeting Summary Re SPDS ML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20238F0381987-09-0909 September 1987 FOIA Request for Copies of Combined Insp Repts 50-317/87-12 & 50-318/87-13 & Reg Guides 1.33 & 1.97 ML20235V1321987-08-28028 August 1987 Forwards EGG-NTA-7471, Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28.... Based on Licensee Responses,Plants Reviewed Conform W/Exceptions Listed in Section 14 ML17342A7741987-07-13013 July 1987 Forwards Technical Evaluation of Rept, Retran Code: Transient Analysis Model Qualification, Dtd Jul 1985. Criteria for Use of Single & Two Loop Plant Models Listed. NRC Audit of Util QA Procedure Recommended ML20235K8731987-07-0909 July 1987 Informs That Tayloe Assoc Cannot Produce Mag or nine-track Tapes of Hearing Transcripts Until NRC Finalizes Arrangements W/Others to Provide Lexis Format,Including Library & File Numbers & Segmentation Info ML20235P0631987-07-0808 July 1987 Forwards Technical Evaluation of Bg&E Topical Rept:Retran Computer Code Reactor Transient Analysis Model Qualification ML20237J2141987-07-0202 July 1987 FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML20215M0431987-05-19019 May 1987 Forwards EGG-NTA-7427, Conformance to Generic Ltr 83-28, Item 2.2.1, 'Equipment Classification for All Other Safety- Related Components,' Calvert Cliffs Units 1 & 2, Final Technical Evaluation Rept ML20234B6211987-05-12012 May 1987 Requests That Listed Plants Be Added to Encl 870508 FOIA Request Re 94300 Region Input on Plant Readiness ML20214R4051987-05-0808 May 1987 FOIA Request for Region Input to NRR Re Status of Listed Plants Readiness for Ol,Per IE Manual Chapter 94300 ML20234B6571987-05-0808 May 1987 FOIA Request for Placement,In Pdr,Region Input to NRC Headquarters,Nrr Re Status of Listed Plants in Terms of Plant Readiness for OL IE Manual,Chapter 94300 ML18052B1531987-05-0101 May 1987 Forwards Final EGG-NTA-7622, Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components:Palisades, Informal Rept ML18150A1861987-05-0101 May 1987 Forwards EGG-NTA-7612, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components,North Anna Units 1 & 2 & Surry Units 1 & 2, Final Informal Rept ML18052B0521987-04-17017 April 1987 Forwards EGG-NTA-7439, Conformance to Generic Ltr 83-28, Item 2.2.1 -- Equipment Classification for All Other Safety- Related Components:Palisades, Final Rept.Facility Conforms to Generic Ltr on Item ML20214R0621987-04-17017 April 1987 Forwards EGG-NTA-7613, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,Arnold, Brunswick-1 & 2, Final Rept.Plants Conform to Item ML20214Q8801987-04-17017 April 1987 Forwards EGG-NTA-7591, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept.Plants Conform to Item ML18150A1171987-04-14014 April 1987 Forwards Final rept,EGG-NTA-7625, Conformance to Item 2.1 (Part 2) Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML18052B0491987-03-30030 March 1987 Forwards EGG-NTA-7484, Technical Evaluation Rept for Palisades Plant,Response to NRR Generic Ltr 83-37, Interim Rept.Licensee Not in Compliance W/Control Room Habitability Requirement (III.D.3.4).Items Still Under Review Listed ML20214R8611987-03-27027 March 1987 Forwards EGG-NTA-7614, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Cook-1 & -2,Haddam Neck, Final Informal Rept.Facilities Conform to Generic Ltr ML20214R1861987-03-26026 March 1987 Forwards Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components,Haddam Neck & Millstone 1,2 & 3, Final 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 ML20211D6631987-02-12012 February 1987 Notifies of 830204 Meeting W/Util,Idvp,Nrc & BNL in San Francisco,Ca to Discuss Status of Containment Annulus Steelwork & Status of Auxiliary Bldg ML20211D7031987-02-12012 February 1987 Notifies of 830209 Meeting in San Francisco,Ca to Discuss Shake Table Tests of Electrical Equipment ML20211D7441987-02-12012 February 1987 Notifies of 830517 Meeting in San Francisco,Ca to Discuss Development of Piping Stress Intensification Factor ML20209A8551987-01-16016 January 1987 FOIA Request for Documents to Be Placed in Pdr,Including NRC Re Calibr of Test Equipment allegation,1986 Inservice Insp Repts for McGuire 1 & Surry 1 & NRC 830307 SALP on Nine Mile Point 2 ML20209F8601987-01-15015 January 1987 Requests Publicly Available Copies of Handouts or Viewgraphs Used at Region III Meeting ML20207K0151986-12-19019 December 1986 FOIA Request That Encls to Insp Rept 50-247/86-26,Byron Semiannual Radioactive Effluent Rept & Millstone 1 & 2 SALP Rept Be Placed in PDR ML20211P2051986-11-24024 November 1986 FOIA Request for La Crosse & Big Rock Point Semiannual Effluent Repts & Turkey Point & St Lucie SALP Repts ML20214R8831986-11-0505 November 1986 FOIA Request for Encls to 860821 SALP Repts ML20213F8841986-10-30030 October 1986 FOIA Request for Encls to NRC 860724 & 31 Requests for Addl Info Re Vermont Yankee Spent Fuel Pool Expansion & Browns Ferry Seismic Reevaluation Program,Respectively 1989-09-07 Category:INCOMING CORRESPONDENCE MONTHYEARML20217N8261999-10-25025 October 1999
[Table view]Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements 1999-09-30 |
Text
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- S-O*Jl1 311' 33,
-:I.Sf" Idaho National Englnflflrlng Laboratwy June 17, 1987 Mr. M. Carrington, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 TRANSMITTAL OF FINAL REPORT, 11 CONFORMANCE TO ITEM 2.1 (PART 2) OF GENERIC LETTER 83-28, REACTOR TRIP SYSTEM VENDOR INTERFACE: CALVERT CLIFFS-1 AND -2, MILLSTONE-2, AND PALISADES, 11 EGG-NTA-7720, JUNE 1987 (FINS D6001 AND ..--D.600*2) - EWR-148-87 .
- Ref: NRC Form 189, 11 Evaluation of Conformance to Generic Letter 83-28 For ORs (Project 2) 11 (D6001); 11 Evaluation of Conformance to Generic Letter 83-28 For OLs (Project 3) 11 (D6002)
Dear Mr. Carrington:
Transmitted herewith is the above subject report.
The report documents INEL's evaluation of the licensee/applicant actions in response to NRC Generic LetteF 83-28, Item 2.1 (Part 2), Reactor Trip System Vendor Interface. Based on the licensee/applicant submittals, we.
conclude that the plants reviewed conform to the generic letter on this item.
E. W. Roberts, Manager NRC Headquarters Support FGF:gp
Enclosure:
As Stated cc: G. L. Jones, DOE-ID D. Lasher, SICB . . _
J. 0. Zane, EG&G Idaho, Inc. (w/o Encl.)
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8707170226 870617 PDR ADOCK 05000255 11
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(::o~ EBt:G ldahO, Inc. 11428 Rockville Pike Suite 410' ; Rockville, MD 20852
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