ML17279A189
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| ML17279A189 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Columbia, River Bend, 05000000 |
| Issue date: | 04/07/1987 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17279A190 | List: |
| References | |
| (NMP2L-1019), NUDOCS 8704130437 | |
| Download: ML17279A189 (6) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999
[Table view]Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARRBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999
[Table view]Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 1999-09-09 Category:UTILITY TO NRC MONTHYEARRBG-33517, Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed1990-09-10010 September 1990
[Table view]Responds to NRC Re Violations Noted in Vendor Interface & Procurement Team Insp Rept 50-458/89-200. Corrective Actions:Maint Instruction Index for Diesel Engine Reviewed RBG-33466, Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range1990-08-30030 August 1990 Responds to Deviations Noted in Insp Rept 50-458/90-16 on 900709-19 Re Suppression Pool Water Level.Corrective Actions:Operator Aids Will Be Developed to Inform Control Room Operators of Actual Instrument Range ML17056A9771990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm. ML18038A3231990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM RBG-33496, Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment1990-08-28028 August 1990 Advises That KT Allbritton No Longer Needs to Maintain License for Facility Due to Termination of Employment RBG-33460, Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.211990-08-28028 August 1990 Forwards Certified Cash Flow Statements for Guarantee of Funds in Event of Retrospective Call Under Secondary Financial Protection Program,Per 10CFR140.21 RBG-33450, Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-9003011990-08-28028 August 1990 Forwards Rev 3 to River Bend Station Updated Fsar. Rev Covers Period 890301-900301 ML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML18038A3221990-08-24024 August 1990 Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors RBG-33424, Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 9009291990-08-22022 August 1990 Requests That Proposed Tech Spec 3.0 & 4.0,when Approved,Be Issued as Effective Immediately W/Implementation to Be Completed by 900929 ML18038A3201990-08-21021 August 1990 Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML18038A3251990-08-20020 August 1990 Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed ML20058Q1151990-08-15015 August 1990 Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21) ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised RBG-33372, Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified1990-08-10010 August 1990 Forwards Semiannual Rept on fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d).No Weaknesses in Program Identified ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns RBG-33310, Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages1990-08-0101 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Rept 50-458/90-06.Corrective Actions:Computer Clock Synchronized to Correct Time & Logic Changed for Making Location Addresses in Retransmission of Messages RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting1990-07-30030 July 1990 Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs RBG-33294, Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank1990-07-26026 July 1990 Forwards Decommissioning Trust Agreement for River Bend Unit 1 & Nuclear Decommissioning Trust Fund Agreement Between Cajun Electric Power Cooperative,Inc & Hibernia Natl Bank ML20055G5261990-07-18018 July 1990 Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl RBG-33196, Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-161990-07-13013 July 1990 Forwards Rev 0 to River Bend Station,Cycle 3 Core Operating Limits Rept Jul 1990. Use of Core Operating Limits Rept in Lieu of cycle-specific Parameters in License Amend Request Approved W/Amend 42 to License,Per Generic Ltr 88-16 ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager RBG-33150, Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed1990-07-0202 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-458/89-11.Corrective Actions:Implementation of New Computerized Tagging Sys Being Developed RBG-33143, Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 19901990-06-29029 June 1990 Addresses Progress of Procurement & Evaluation Activities for Sys to Meet Reg Guide 1.97 Neutron Monitoring Requirements.Bid Spec to Incorporate NRC & BWR Owners Group Guidance Will Be Issued Prior to Fourth Quarter 1990 ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) RBG-33132, Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs1990-06-28028 June 1990 Suppls Response to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Reverify Switch Settings on Initial Surveillance Interval of 5 Yrs ML17058A5841990-06-27027 June 1990 Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2 ML18038A3051990-06-26026 June 1990 Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl RBG-33113, Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License1990-06-26026 June 1990 Requests Implementation of Generic Ltr 87-09 Wording for Bases for Spec 4.0.3 Re Reporting Requirements of 10CFR50.73 for Missed Surveillances to Enable NRC to Continue Review of 880930 Application for Amend to License RBG-33120, Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads1990-06-26026 June 1990 Responds to 900621 Request for Addl Info Re Effects on Containment Dynamic Loads Which Will Result from Increasing Suppression Pool Temp from 95 F to 100 F.Original Design Basis of 100 F Included in Steam Condensation Loads RBG-33114, Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon1990-06-26026 June 1990 Requests Withdrawal of 900202 Application for Amend to License NPF-47,revising Div I & II Diesel Generator Crankshift Insp Scheduling,Per 900529 Telcon RBG-33100, Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 19901990-06-22022 June 1990 Requests Waiver of Compliance W/Tech Spec 3/4.6.3.1 Until Exigent Processing of Tech Spec Change Request LAR 90-08 Completed.Change Revises Max Temp for Suppression Pool to 100 F to Avoid Limiting Plant Operation in Jul & Aug 1990 ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle 1990-09-10 |
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REQULATO NFORNATION DISTRIBUTION TTEN <RIDS) o
-ACCESSION NBR: 8704130437 DOC. DATE: 87/04/07 NOTARIZED: YES , DOCXET e FAG IL: 50-000 Generic Doc ket 05000000 50-397 MPPSS Nuclear Prospect Unit 2 Nash ington Public Pore 05000397 50-410 Nine Nile Point Nuclear Station> Unit 2> Niagara aloha 05000410 50-458 River Bend Stations Unit 11 Gulf States Utilities Co. 05000458 AUTH. NANE NANQAN> C. V.
RECIP. NAl'1E AUTHOR AFFILIATION Niagara Mohawk Poser Corp.
RECIPIENT AFFILIATION gCC. IO~
Document Control Branch (Document Control Desk)
SUBJECT:
Forwards "Comparison of Electrical Design of Wge Pattern Globe Valve Actuator M/Bali Valvei Hanford 2 Zc River Bend Design." for use h info.
DISTRIBUTION CODE: AOOID TITLE: OR COPIEB RECEIVED: LTR Submittal: General Distribution I ENCL / SIZE: R~S NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAl'lE LTTR ENCL ID CODE/NAME LTTR ENCL PD5 L* 0 PD1-1 L* 1 0 PD4 LA 1 0 PD5 PD 5 5 PD1-1 PD 5 5 PD4 PD 5 5 SANWORTH R 1 HAUGHEY> M 1 1 llINERi 8 1 1 STERNI 8 1 QhJTER NAL: ACRS h 6 ADN/LFNB 1 0 NRR/DEBT/ADE 1 1 NRR/DEST/ADS 1 1 NRR/DLPG/HFB 1 MRR/DOEA/TSB 1 NRR/Pl'fAS/ILRB 1 1 -8 82 0 OQC/HD81 0 REG FI 01 1 1 EXTERNAL: EQSQ BRUSKEi 8 1 1 LPDR NRC PDR 1 NSlC
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TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 38
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NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELO ROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 8704130437 870407 PDR *DOCK 050003'P7' PDR April 7, 1987 (NMP2L 1019)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Nine Mile Point Unit 2 Docket No. 50-410 Gentlemen:
Enclosed for your use and information is a report that compares the electrical design of the Nine Mile Point Unit 2 wye pattern globe valve presently being installed with the ball valve design. The report also compares the wye pattern globe valve electrical'design for Unit 2 with the Hanford 2 and River Bend electrical design.
This information was discussed with the Nuclear Regulatory Commission staff on April 2, 1987, and is provided to support review of the wye pattern globe valve design. For your information, there is no restriction on copying any of the drawings included in this submittal. If there are questions, please contact Mr. lallnick of my staff.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION C. V. Mang Senior Vice President NLRlpns 2976G Enclosure xc: Regional Administrator, Region I Project Director d(lL Ms. E. G. Adensam, Mr. W. A. Cook, Resident Inspector '
/t ggd Project File (2) , >%hah
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Hatter of l l
Niagara Mohawk Power Corporation ] Docket No. 50-410
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(Ni ne Mile Po I n t Unit 2) l AFFIOAVIT C. V. Han an , being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that al.l such documents are true and correct to the best of his knowledge, information and belief.
Subscribed and sworn to before me, a Notary Public in and for the State of New York and County of , this 7 . day of , 1987.
Notary Public in and for County, New York Hy Commission expires:
MAP( FBATESCHI Notary Public In the State of New Yorrr Quelllled In Onondaga County No. 4797550 Lly Commlselon Explroa March 3'9gg
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