|
|
Line 153: |
Line 153: |
| 4 p - | | 4 p - |
|
| |
|
| ;
| | CfW-79-10 T |
| CfW-79-10 | | (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product. |
| ;
| |
| T (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
| |
| (d) It reveals cost or price information, production capaci-ties, budget levels, or comercial strategies of Westing-house, its customers or suppliers. | | (d) It reveals cost or price information, production capaci-ties, budget levels, or comercial strategies of Westing-house, its customers or suppliers. |
| (e) It reveals aspects of past, present, or future Westing-house or customer funded development plans and programs of potential commercial value to Westinghouse. | | (e) It reveals aspects of past, present, or future Westing-house or customer funded development plans and programs of potential commercial value to Westinghouse. |
Line 169: |
Line 167: |
| **W - 4?w=% e .wg. | | **W - 4?w=% e .wg. |
|
| |
|
| ; .
| |
| ~ | | ~ |
| CAW-79-10 l (v) The proprietary information sought to be withheld in this sub-mittal are the transparencies utilized by Westinghouse in its | | CAW-79-10 l (v) The proprietary information sought to be withheld in this sub-mittal are the transparencies utilized by Westinghouse in its |
Line 178: |
Line 175: |
| it would reveal the details of the test setup, the hydraulic test results, hydraulic calculations, and the conclusions of the Westinghouse fuel development program for Millstone 2 and similar plants, which is recognized by the Staff to be of competitive value and because of the large amount of effort and money expended by Westinghouse in carrying out this development program. | | it would reveal the details of the test setup, the hydraulic test results, hydraulic calculations, and the conclusions of the Westinghouse fuel development program for Millstone 2 and similar plants, which is recognized by the Staff to be of competitive value and because of the large amount of effort and money expended by Westinghouse in carrying out this development program. |
| Information regarding its development programs is valuable to Westinghouse because: | | Information regarding its development programs is valuable to Westinghouse because: |
| (a) Information resulting from its development programs gives Westinghouse a competitive advantage over its com- | | (a) Information resulting from its development programs gives Westinghouse a competitive advantage over its com-petitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position. |
| ;
| |
| petitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position. | |
| e e . w. . . | | e e . w. . . |
|
| |
|
|
---|
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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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) 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) 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 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) 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 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl 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 ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program 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 ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 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 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 ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene 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 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 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 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 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 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 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 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 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) 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 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) 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 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 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 ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures 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) 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 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 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 B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8071990-09-11011 September 1990 Forwards Core Operating Limits Rept for Four & Three Loop Operation,Per Tech Spec 6.9.1.6.d A08900, Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access1990-09-11011 September 1990 Responds to Expressing NRC Views on Access to Util Internal or third-party Assessment Repts.Believes Internal Analysis to Support Amend of One of Util NRC OLs to Authorize Higher Power Level Is within NRC Purview & Access B13628, Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel1990-09-0707 September 1990 Forwards Correction to Error Discovered in Util 900727 Response to Notice of Violation from Insp Rept 50-336/90-09. Statement Corrected to Read That Contract Personnel That Have long-term Assignments,Certified as Testing Personnel B13624, Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon1990-09-0505 September 1990 Forwards Addl Info Re Relief Request from ASME Code Section XI Requirements for Temporary Repair to Piping Adjacent to Valve 2-SW-97A,per 900817 Telcon A08977, Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage1990-09-0404 September 1990 Advises of Commitment to Install Hardened Wetwell Vent at Facility,In Response to NRC .Util Will Be Proceeding W/Initial Design & Engineering of Hardened Vent, to Support Installation During 1993 Refueling Outage B13626, Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility1990-08-31031 August 1990 Informs That Info Provided in Re safety-related Equipment Classification Programs Also Applicable for Unit 3 of Facility B13596, Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed1990-08-31031 August 1990 Forwards Millstone Unit 3 Individual Plant Exam for Severe Accident Vulnerabilities, Per Generic Ltr 88-20.Rept Identified That No Major Severe Accident Vulnerabilities Requiring Corrective Action Needed B13618, Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-031990-08-24024 August 1990 Forwards Addl Info on Util 900815 Relief Request from ASME Code Section XI Requirements,Per 10CFR50.55a(g)(6)(i),for Repairs to Pipe 3SWP-006-050-03 ML20059C2061990-08-23023 August 1990 Forwards Vols 1 & 2 to Semiannual Radioactive Effluents Release Rept Jan-June 1990, Per 10CFR50.36a.Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents A08918, Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided1990-08-22022 August 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-245/90-08.Mitigation of Civil Penalty Requested.Corrective Action:List of Procedural Changes Provided B13610, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps1990-08-15015 August 1990 Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Re Mods to Pipe 3SWP-006-050-03. Results of Insps & Required Repairs Will Determine Schedule for Future Insps B13595, Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-13941990-08-14014 August 1990 Notifies NRC That Utils Volunteer to Participate in Emergency Response Data Sys Project for All Four Nuclear Units,Per Generic Ltr 89-15 & NUREG-1394 B13607, Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-051990-08-10010 August 1990 Requests Relief from ASME Code Section XI to Reflect Mod to Piping Adjacent to Valve 2-SW-97A,in Response to Generic Ltr 90-05 A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision1990-08-0808 August 1990 Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision ML20058N2181990-08-0707 August 1990 Notification of Change in Senior Operator Status.Util Determined That Need to Maintain Senior OL of LS Allen No Longer Exists.Determination Effective 900719 ML20058M8321990-08-0707 August 1990 Discusses Spent Fuel Racks Poison Surveillance Coupon Boraflex Degradation.Visual Exam of Remaining Surveillance Coupons Revealed Similar Situation Existed in All Coupon Samples B13590, Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise1990-08-0101 August 1990 Responds to NRC 900718 Request for Addl Info Re Util 900418 Request for Schedular Exemption from 10CFR50,App E,Section IV.F.3 to Allow Dec 1990 Full Participation Exercise to Be Exchanged W/Oct 1991 Partial Participation Exercise A08881, Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event1990-07-31031 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-423/90-08.Corrective Action:Operators Directly Involved W/Event Removed from Licensed Duties & Counseled by Operations Manager on Causes of Event B13594, Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))1990-07-30030 July 1990 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a)) ML20055J4621990-07-27027 July 1990 Advises That Need to Maintain OL or Senior OL for Listed Individuals No Longer Exists,Effective 900701 A08565, Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities1990-07-26026 July 1990 Responds to NRC 900302 Request for Addl Info Re LPCI Swing Bus Transfer Design & Single Failure Vulnerabilities B13585, Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys1990-07-26026 July 1990 Provides Supplemental Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of Unresolved Safety Issue A-47.Plant Procedures Modified to Provide Operability Verification of Steam Generator Protection Sys B13592, Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent1990-07-24024 July 1990 Requests Extension to Respond to NRC Backfit Analyses of Hardened Wetwell Vent ML20063P9791990-07-23023 July 1990 Notification of Change in SL Jackson Status Effective 900701,due to Permanent Reassignment within Util B13566, Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage1990-07-20020 July 1990 Advises That Util Has Reasonable Assurance That Safety Relief Valves Operable & Will Perform as Expected Until Next Outage B13563, Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety1990-07-20020 July 1990 Discusses Util Comprehensive Review of Options Re Degraded Grid Undervoltage Protection.Confirms Previous Conclusion That Splitting Loss of Normal Power Logic Would Have Overall Adverse Impact on Plant Safety ML20055G5331990-07-18018 July 1990 Forwards Decommissioning Financial Assurance Certification Rept A08822, Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-971990-07-18018 July 1990 Submits Addl Info Requested Re Util Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Charpy Impact Use Values for Welds Provided in Evaluation of Irradiated Capsule W-97 B13588, Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged1990-07-18018 July 1990 Corrects 900703 Submittal of Results of Second in-cycle Insp of Steam Generators.All Tubes W/Cracks Stacked & Plugged B13587, Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components1990-07-16016 July 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.5.F.2 Re Emergency Diesel Generator (EDG) Limiting Condition for Operation.Waiver Would Extend Available Time to Repair Damaged Electrical Components ML20055D3461990-07-0303 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil Transmitters Mfg by Rosemount.Operability Determinations Performed & Documented for All Rosemount 1153 & 1154 Transmitters at Facility ML20055D3481990-06-29029 June 1990 Forwards Addl Info Re Facility Crdr & Isap,Including Justification for Human Engineering Discrepancies Dispositioned for No Corrective Action ML20055D7191990-06-29029 June 1990 Amends 900604 Rev 13 to QA Program B13545, Forwards Rev 3 to Updated FSAR for Millstone Unit 31990-06-29029 June 1990 Forwards Rev 3 to Updated FSAR for Millstone Unit 3 B13550, Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl1990-06-27027 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Implementation & Completion Tables for staff-imposed Requirements Encl B13499, Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys1990-06-26026 June 1990 Forwards Corrected Tech Specs Page 3/4 9-1 for Incorporation Into Proposed Amend 36 to License DPR-21 Re Auxiliary Electrical Sys ML20043F8721990-06-11011 June 1990 Corrects Name of Vendor Supplying Replacement Plug Valves, Per Util 900511 Ltr.Replacement Bolts,Not Valves,Purchased from Cardinal Industrial Products Corp ML20043H0161990-06-0808 June 1990 Requests Exemption from App J to 10CFR50 for 12 Valves in Reactor Bldg Closed Cooling Water Sys.Valves Not within Definition of Containment Isolation Valves in App J & Not Required to Be Tested ML20043E8831990-06-0505 June 1990 Requests NRC Authorization to Use Plugs Fabricated of nickel-chromium-iron Uns N-06690 Matl Alloy 690 to Plug Tubes in Steam Generators of Plant ML20043D0451990-05-30030 May 1990 Discusses Proposed Rev to Tech Specs Re Facility ESF Actuation Sys Instrumentation Trip Setpoint,Per 900330 Ltr ML20042H0311990-05-0909 May 1990 Discusses Steam Generator Safety Assessment.Concludes That Continued Operation Through Remainder of Current Cycle 10 Fully Justified ML20042F0941990-04-30030 April 1990 Provides Addl Info Re Environ Impact of 900226 Application for Amend to License NPF-49,revising Tech Specs to Allow Containment Pressure to Increase to 14 Psia During Modes 1-4,per NRC Request ML20042F0661990-04-30030 April 1990 Responds to NRC 900404 Ltr Re Violations Noted in Safety Insp Rept 50-336/90-01 on 900120-0305.Corrective Action:Ler 90-004 Submitted on 900430 to Document Condition Prohibited by Plant Tech Specs ML20042E8331990-04-27027 April 1990 Forwards Annual Environ Protection Plan Operating Rept for 1989, & Monitoring Marine Environ of Long Island Sound at Millstone Nuclear Power Station Annual Rept 1989. ML20012E2681990-03-23023 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-423/89-23.Corrective Actions:Requirement to Review All Changes on Safety Sys for Potential Operating Procedure Changes Stressed to Operations & Engineering Personnel ML20012C3141990-03-13013 March 1990 Forwards Info Re Insp of Facility Emergency Operating Procedures,Per 900119 Ltr ML20012B4111990-03-0202 March 1990 Provides Addl Info Requested to Clarify Changes Proposed to Tech Spec Action Statements for Inoperable Accumulator B13453, Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably1990-02-26026 February 1990 Advises That Mods to Steam Generator Blowdown Sample Sys Completed,Per Violations Noted in Insp Rept 50-423/89-14 & Salp.Sys Will Be Evaluated for Next 2 Wks to Ensure Blowdown Radiation Monitor Operating Reliably ML20011F7541990-02-26026 February 1990 Notifies That Jh Parillo Reassigned & No Longer in Need of License SOP-10263-2 as of 900219 ML20006G1581990-02-21021 February 1990 Forwards Response to & Comments on Initial SALP Rept 50-423/88-99 for Period 880601 - 891015.Procedures Revised to Permit Operators to Adjust Area Monitors to Reduce Nuisance Alarms 1990-09-07
[Table view] |
Text
-
NORTHEAST IFFII.FFIES
] . .. [N .'.P E*,.2 '."* P o BOX 270
.ii ...y,s . .
t N
March 6, 1981 y[ %
v Docket No. 50-336 s'M@
~
9 A01155 s p 7 -
/.
F $
L
- 'l G Director of Nuclear Reactor Regulation Attn
- Mr. Robert A. Clark, Chief C f j g
$/[/[
Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission
\q' .
-Q' _.
1
/)'
Washington, D.C. 20555
References:
(1) W. G. Counsil letter to R. Reid, dated March 6, 1980.
(2) T. M. Novak letter to W. G. Counsil, duted August 6,1980.
(3) W. G. Counsil letter to R. A. Clart, dated January 16, 1981.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Hydraulic Flow Test of the Fbdel C Prototype Fuel Assembly By Reference (1), Northeast Nuclear Energy Company (NNECO) docketed the Basic Safety Report (BSR) in support of Cycle 4 operation of Millstone Unit No. 2.
In Reference (2), the NRC Staff requested that ICIECO provide information in support of the Reference (1) discussions of the Fuel Assembly Test System (FATS) and the hydraulic compatibility testing which was performed for the Model C fuel assembly.
Accordbgly, N'IECO hereby provides the non-proprietary and proprietary versions of the test report , " Hydraulic Flow Test of the hbdel C Prototype Fuel Assembly,"
as attachments 2 and 3 respectively.
Due to the proprietary nature of portions of the material contained in Attachment 3, NNECO respectfully requests that it be withheld from public disclosure in accordance with the provisions of 10CFR2 790 and that this caterial be safeguarded.
The reasons for the classification of this material as proprietary are delineated in the Application for Withholding Proprietary Information and the accompanying affidavit included as Attachment 1.
h k
8103160359
l 1
. . 1 With the docketing of this material, NNECO has responded to each of the Staff's questions identified to date in the review of the BSR. As noted
{
in Reference (3), it is our intent to conduct future reloads of Millstore '
Unit No. 2 under the provisions of 10CFR50.59 The BSR is a necessary i and integral document for successfully implementing these plans.
We trust you find the attached information satisfactory and remain available to respond to any questions which you may identify during the review of Reference (1).
Very truly yours, NORTH 2AST IiUCLEAR ENERGY COMPANY 7
). A iT W. d. Counsfl Senior Vice President
. s Docket No. 50-336 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Application for Withholding Proprietary Information from Public Disclosure
/
March, 1981
. i Westinghouse Water Reactor weensa omon Electric Corporation Divisions , 33 PittstarghPennsvban915230 January 27, 1981 CAW-81-7 Director of Nuclear Reactor Regulation Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTN: Mr. Robert A. Clark, Chief APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
SUBJECT:
WCAP-9551 (Proprietary) and WCAP-9833 (Non-Proprietary),
" Hydraulic Flow Test of the Model C Prototype Fuel Assembly" REF: (1) R. A. Wiesemann letter to R. Reid dated March 21, 1979 (2) T. M. Novak letter to W. G. Counsil dated August 6,1980 (3) Northeast Utilities letter W. G. Counsil to R. A. Clark, February 1981
Dear Mr. Clark:
The proprietary material for which withholding is being requested by Northeast Nuclear Energy Company (NNECO) is of the same technical type as that previously submitted in Reference 1. Further, the affidavit submitted to justify the material previously submitted, CAW-79-10, is equally applicable to this material. The subject material is being submitted in response to a request for addition:sl informatica transmitted via Reference 2.
Accordingly, withholding the subject information from public disclosure is requested in accordance with the previously submitted affidavit and application for withholding, CAW-79-10, dated March 21, 1979, a copy of which is attached.
Correspondence with respect to this application for withholding or the accom-panying affidavit should reference CAW-81-7 and should be addressed to the undersigned.
Very truly yours, delKc1Rth Robert A. Wiesemann, Manager
/bek
- Enclosure Regulatory & Legislative Affairs _
cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC
". H.
Westinghouse Electric Corporation Power Systems re.ns,s:asc< a kin:
Pittsu,tgi Pem<,w.a 15211 March 21,1979 i
CAW-79-10 Director of Nuclear Reactor Regulation Attn: Mr. R. Reid, Chief Operating Reactors Branch #4 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i
APPLICATION FOR WITHHOLDING 790PRIETARY INFORMATION FROM PUBLIC DISCLOSURE
SUBJECT:
Millstone Nuclear Power Station, Unit No. 2 (Docket Number 50-336) Information Presented at the January 26, 1979 Meeting with the NRC REF: Northeast Nuclear Energy company Letter from W. G. Council to R. Reid dated March 21, 1979 Gentlemen:
This application for withholding is submitted by Westinghouse Electric Corporation pursuant to the provisions of paragraph (b)(1) of 10CFil Section 2.790 of the Commission's regulations.
The accompanying affidavit identifies the information sought to be with-held from public disclosure, sets forth the basis on which the inforna-tion may be withheld from public disclosure by the Commission, and
- addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
The undersigned has reviewed the information sought to be withheld and is authorized to apply for its withholding on behalf of Westinghouse, WRD, notification of which was sent to the Secretary of the Commission on April 19, 1976.
- It is requested, therefore, that the Westinghouse proprietary information being transmitted by the Northeast Nuclear Energy Company letter referenced above be withheld from public disclosure in accordance with the provisions of 10CFR Section 2.790 of the Commission's regulations.
s
@= - w + g musempe w see t $wqMe _. _44mam ewwape ep
_gg
c i . . .
! Mr. R. Reid -
March 21,1979 .
CAW-79-10 l
- Correspondence with respect to the proprietary aspects of this applica- .
tion for withholding or the accompanying affidavit should reference '
CAW-79-10 and should be addressed t1 the undersigned.
! i i
Very truly yours, !
'l .
i afw i
Robert A. Wiesemann, Manager Regulatory & Legislative Affairs t
/bek Attachment
- cc
- J. A. Cooke, Esq.
Office.of the Executive Legal Director 1 .
]
1 i
e O
h e
9
l
.: . . l l
l l
CAW-79'10 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss ,
COUNTY OF ALLEGHENY:
i Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric C,orporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
AAAlMLA M Robert A. Wiesemann, Manager Regulatory & Legislative Affairs Sworn to and subscribed before me th s 4 day of 71/ 1979.
14 uMAX
/ NotaryPudic/
9 4
t 3 . .. . __ -.
1 CAW-79-10 (1) I am Manager, Regulatory and Legislative Affairs, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions, (2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in con-junction with the Westinghouse application for withholding accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.h90 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the infor-mation sought to be withheld from public disclosure should be withheld. '
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
e G
- e==ae es.rwe .+eeee.e==.-- .-e. . . . . m.. %, ,.
. CAW-79-10 (ii) The information is of a type customarily held in confidence by Westinghouse and.not customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitutes Westinghouse. policy and provides the rational basis required.
In determining whether information in a document or report is proprietary, the %11owing criteria and standards are ' utilized in Westinghouse. Information is proprietary if any one of the following are met:
(a) The information reveals the distinguishing aspects of a -
process (or component, structure, tool, method, etc.)
where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes
, a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
4 p -
CfW-79-10 T
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
(d) It reveals cost or price information, production capaci-ties, budget levels, or comercial strategies of Westing-house, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westing-house or customer funded development plans and programs of potential commercial value to Westinghouse.
( f.) It contains patentable ideas, for which patent protection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to 1
agreements with the owner.
(iii) The information is being transmitted to the Commission in con-fidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not available in public sources to the best I_ of our knowledge and belief.
1 4
e O
*& u e_ .w __ -
~
CAW-79-10 l (v) The proprietary information sought to be withheld in this sub-mittal are the transparencies utilized by Westinghouse in its
, presentation to the fiRC at the January 26, 1979 meeting con-cerning review of the Millstone 2 reload safety evaluation.
This information includes photographs of test hardware, physical dimensions of fuel assemblies, hydraulic test results and hydraulic calculations. The letter and transparencies are 4
being submitted in response to the request of the Comission at the January 26, 1979 meeting.
Public disclosure of this information is likely to cause s Jb-stantial harm to the competitive position of Westinghouse as .
it would reveal the details of the test setup, the hydraulic test results, hydraulic calculations, and the conclusions of the Westinghouse fuel development program for Millstone 2 and similar plants, which is recognized by the Staff to be of competitive value and because of the large amount of effort and money expended by Westinghouse in carrying out this development program.
Information regarding its development programs is valuable to Westinghouse because:
(a) Information resulting from its development programs gives Westinghouse a competitive advantage over its com-petitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
e e . w. . .
i CAW-79-10 I
(b) It is information which is marketable in many ways. The extent to which such information is available to ccepeti-tors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a com-petitive disadvantage by reducing his expenditure of resources at our expense. -
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If ccm- -
petitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
This information enables Westinghouse to:
(a) Justify the design basis for the fuel (b) Assist its customers to obtain licenses (c) Meet warranties Further, this information has substantial commercial value as follows:
(a) Westinghouse sells the use of the information to its customers for purposes of meeting NRC requirements for licensing documentation.
m - 4 e,M_e-emuumme . i ew= _- a, .mese . w e ~. m es *- a -
.b -
CAW-79-10 (b) Westinghouse uses the information to perform and justify analyses which are sold to customers.
(c) Westinghouse uses the information to sell nuclear fuel and related services to its customers.
Public disclosure of this information is likely to cause substan-tial harm to the competitive position of Westinghouse in selling nuclear fuel and related services.
Competitors could obtain the equivaient information, with difficulty, by investing similar sums of money and provided they had the appropriate resources available and the requisite experience.
Further the deponent.sayeth not.
O 8
6 4
9' Mhmmmm._._m.___._m_ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . -