IR 05000410/1983006
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| ML20154H718 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/03/1986 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Hooten B NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8603100360 | |
| Download: ML20154H718 (2) | |
Similar Documents at Nine Mile Point | |
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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 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 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 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 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 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 ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 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 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 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 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 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 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 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 ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 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 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. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr 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) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07 Category:NRC TO UTILITY MONTHYEARML20062G7671990-11-21021 November 1990
[Table view]Advises That Financial Info Submitted for 1990 Satisfies 10CFR140 Re Guarantee of Deferred Premiums ML20059F5351990-09-0606 September 1990 Advises That Request to Extend Date to Submit Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Denied Due to Safety Significance of Issue IR 05000220/19900061990-07-31031 July 1990 Forwards Insp Repts 50-220/90-06 & 50-410/90-06 on 900531-0712 & Notice of Violation.Corrective Actions Did Not Identify Addl Blue mark-up Controlled Components Which Were Out of Position & Subsequently Discovered by Inspector ML20059M9301990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20012E5921990-03-28028 March 1990 Advises of Requalification Program & Licensed Personnel Evaluation Scheduled for Wks of 900709 & 16 ML20012C6411990-03-19019 March 1990 Forwards NRC Understanding of Current Status of Unimplemented USIs for Plant ML20012D3201990-03-16016 March 1990 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 900709 & 16.NRC Examiners Will Visit Site Approx 14 Days Prior to Evaluation.Ref Matls,Listed on Encl,Should Be Furnished ML20006D6111990-01-24024 January 1990 Discusses Generic Fundamentals Exam Section of Written Operator Licensing Exam Per Generic Ltr 89-17 ML20006D6921990-01-0505 January 1990 Forwards Revised NRC Forms 398, Personal Qualifications Statement - Licensee & 396, Certification of Medical Exam by Facility Licensee, Respectively.Applications for Licenses Should Be Submitted on Revised Forms by 900201 ML20248D3531989-09-25025 September 1989 Forwards Amend 18 to Indemnity Agreement B-36,reflecting Changes to 10CFR140,effective 890701 ML20247A0611989-05-0404 May 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Technical Evaluation Rept Also Encl ML20195J1011988-11-29029 November 1988 Forwards Amend 102 to License DPR-63 & Safety Evaluation. Amend Revises Tech Spec 6.2 to Make Table 6.2-1 Consistent W/Requirements of 10CFR50.54(m)(2)(i) & 6.2.2.e to Clarify Staffing Required During Hot Shutdown ML20206K7071988-11-18018 November 1988 Forwards Insp Repts 50-220/88-30 & 50-410/88-29 on 880926-30.No Violations Noted IR 05000220/19882011988-10-26026 October 1988 Provides Summary of Significant Findings in Advance of Insp Rept 50-220/88-201,so That Appropriate Corrective Actions May Be Factored Into Restart Planning Activities.Issues That Must Be Resolved Before Sys Declared Operable Listed ML20155E2091988-10-0404 October 1988 Forwards Exemption from 10CFR50.54(w)(5)(i) Requirements Re Property Insurance Rule Effective 881004.Rule Requires Licensees to Obtain Insurance Policies That Prioritize Insurance Proceeds for Stabilization & Decontamination ML20150E9351988-07-0101 July 1988 Forwards Amended SALP Repts 50-220/86-99 & 50-410/87-99 for Nov 1986 - Feb 1988 & Feb 1987 - Feb 1988,respectively ML20155F4111988-06-10010 June 1988 Forwards Safety Insp Repts 50-220/88-09 & 50-410/88-09 on 880307-11 & 0404-08 & Notice of Violation ML20237C1091987-12-11011 December 1987 Forwards Safety Insp Rept 50-220/87-22 on 871019-23.No Violations Noted ML20237A3341987-12-0808 December 1987 Informs of Written & Operating Exams Scheduled for Wk of 880229.Requests That Ref Matl Listed in Encl Be Provided as Scheduled.Reactor Operator License Applications Should Be Submitted 30 Days Before First Exam ML20236B5821987-10-15015 October 1987 Forwards Exam Rept 50-220/87-16OL of Exam Administered During Wk of 870803.Related Info Also Encl ML20235Q9291987-10-0101 October 1987 Forwards Combined Requalification & Replacement Exam Rept 50-410/87-18OL Administered on 870707-09.Final Program Evaluation Will Be Issued Following Next Set of Requalification Exams ML20235J1311987-09-23023 September 1987 Forwards Safety Insp Repts 50-220/87-15 & 50-410/87-24 on 870803-07.No Violations Noted ML20238A8771987-08-31031 August 1987 Recommends That Site Specific Info Sheets & Appropriate Training Re Use Be Developed & Provided to Emergency Notification Sys & Health Physics Network Communicators to Facilitate Responses to NRC Requests for Data.Samples Encl ML20237H5441987-08-12012 August 1987 Forwards Results of Nonradiological Chemistry Stds Insp Activities for All Region I Licensees During 1985-1986. Results of Measurements Made by BNL Also Included ML20236K0701987-07-29029 July 1987 Informs of Results of Review of Util Responses to Item 2.1, Generic Ltr 83-28, Equipment Classification & Vendor Interface (Reactor Trip Sys Components). Requirements Met ML20245C1671987-06-22022 June 1987 Forwards Exam Rept 50-220/87-05OL of Exam Administered During Wk of 870406-09 ML20214S5471987-06-0404 June 1987 Forwards Revised NRC Form 398, Personal Qualifications Statement - Licensee. Rev Made to Reflect Changes to 10CFR55 Effective 870526.All Applications for Licenses to Be Submitted on Revised Form as of 870526 ML20210D1921987-04-29029 April 1987 Advises That Operator Requalification Program Evaluation Scheduled for Wk of 870706,per Telcon.Ref Matl Listed in Encl 1 Should Be Furnished by 870511 ML20205G8441987-03-25025 March 1987 Forwards Safety Insp Rept 50-410/87-05 on 870202-05.No Violations Noted ML20204F3051987-03-18018 March 1987 Forwards Insp Rept 50-410/87-03 on 870112-28.No Violations Noted ML20207S7951987-03-17017 March 1987 Forwards Exam Rept 50-410/86-69OL on 861210 ML20204F0751987-03-16016 March 1987 Forwards Safety Insp Rept 50-410/87-07 on 870209-13.No Violations Noted ML20207S5891987-03-12012 March 1987 Forwards Safety Insp Rept 50-410/87-06 on 870210-13.No Violations Noted.Steps Taken to Correct Deviation Noted in NRC Verified ML20207R6441987-03-11011 March 1987 Forwards Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable.Eg&G Technical Evaluation Rept Encl IR 05000220/19860071987-03-0909 March 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-220/86-07 ML20211F5721987-02-17017 February 1987 Forwards Radiological Controls Insp Repts 50-220/87-02 & 50-410/87-04 on 870112-16.No Violations Noted.Weaknesses in ALARA Program & in Control of Portal Monitors Identified ML20211A3121987-02-11011 February 1987 Forwards Insp Repts 50-220/86-26 & 50-410/86-65 on 861117-870104 & Notice of Violation.Activities Re Maint of Reactor Bldg Integrity & Corrective Action for Unplannned Scram While Shut Down Violated NRC Requirements IR 05000410/19860561987-02-0404 February 1987 Discusses Safety Insp Rept 50-410/86-56 on 861001-1116 & Forwards Notice of Violation.Violations Demonstrate Need for Addl Training & Improved Oversight of Operations to Assure That Plant Operated in Accordance W/Tech Specs ML20212K9991987-01-22022 January 1987 Forwards Insp Repts 50-220/86-17 & 50-410/86-61 on 860825- 29.No Violations Noted.Programmatic Weaknesses in Mgt Sys Noted & Should Be Addressed.Enforcement Conference Will Be Scheduled to Discuss Apparent Violations & Weaknesses ML20212H7391987-01-16016 January 1987 Forwards Insp Rept 50-410/86-67 on 861201-05.No Violations Observed ML20207Q3571987-01-14014 January 1987 Forwards Safety Evaluation Re MSIV Logic Mods Resulting from 861203 Full Scram,Per 861218 & 870106 Meetings.Mods Do Not Meet Requirements of 10CFR50,App A,Gdc 21 or IEEE Std 279.Issue Must Be Resolved Before Initial Criticality ML20212G7771987-01-13013 January 1987 Forwards Safety Insp Rept 50-410/86-68 on 861208-12.No Violations Noted ML20207P3971987-01-13013 January 1987 Informs of Lasl 870323-26 Site Visit to Conduct Analysis in Order to Identify Areas in Which Sabotage Actions Could Result in Radiological Releases in Excess of 10CFR20 Limits. Listed Diagrams Should Be Provided to Lasl ML20207K3261987-01-0202 January 1987 Forwards Insp Rept 50-220/86-24 on 861103-07.No Violations Observed.Rept Identifies Addl Example of Concern Re Lack of Conformance to Approved Procedures (Ref Insp Rept 50-220/86-13) ML20207K2311986-12-31031 December 1986 Forwards Safety Insp Repts 50-220/86-27 & 50-410/86-66 on 861201-05.No Violations Observed ML20207F0461986-12-29029 December 1986 Forwards,For Info,Bwr Owners Group NEDE-31096-P, ATWS; Response to NRC ATWS Rule,10CFR50.62. Info Submitted on 850521 in Lieu of Participation in Owners Group Topical Rept Under Review.Results Will Be Forwarded Upon Completion ML20207J4381986-12-24024 December 1986 Forwards Insp Rept 50-410/86-53 on 860922-26.No Violation Noted ML20207N4031986-12-23023 December 1986 Forwards Notice of Violation from Investigation Rept 1-84-014.Investigation Conducted in Response to Allegations That Util QA Auditors Harassed & Intimidated as Result of Findings of QA Audit 84-4 Conducted in Jan & Feb 1984 ML20207F1461986-12-19019 December 1986 Forwards,For Info,Safety Evaluation Re BWR Owners Group NEDE-31096-P, Atws;Response to NRC ATWS Rule,10CFR50.62. Confirmation of Applicability of Topical Rept & Response to Listed Concerns Requested within 90 Days ML20207N0621986-12-18018 December 1986 Forwards Insp Rept 50-220/86-13 on 860910-12 & 15-19. Concerns Raised Re Inadequacy of Control of Operations, Surveillance,Maint & Mod Activities.Actions to Control Vendor Technical Info Not Responsive to Generic Ltr 83-28 1990-09-06 Category:OUTGOING CORRESPONDENCE 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 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 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 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 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 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 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 ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20195F9971999-06-11011 June 1999 Discusses 990513 Fax Which Forwarded Copy of an Open Ltr to Central New York on Nine Mile One Nuclear Reactor, & Petition to NRC Re Nine Mile Point One Core Shroud Insp, Signed by 187 People ML20195G9661999-06-11011 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990524.Petition Requested That NRC Suspend Operating License Issued to NMP for Nine Mile Point Unit 1.Staff Reviewing Issues & Concerns Raised in Petition ML20207H1021999-06-10010 June 1999 Advises That Info Re Theoretical Basis for Shear & Torsional Spring Constants in Holtec Sf Rack, Submitted in & Affidavit ,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20207G5281999-06-0909 June 1999 Ack Receipt of Expressing Concern for Reactor Core Shroud for Plant,Unit 1.NRC Staff Requested to Conduct Insp of Reactor Shroud,Including Areas Outside Core Shroud Welds & Publicly Disclose Results 1 Wk Before Plant Restart ML20137S9381999-06-0909 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990405.Petition Requested That NRC Take EA Against Util & Senior Nuclear & Corporate Mgt ML20207H3961999-06-0707 June 1999 Informs That NRC NRR Reorganized,Effective 990328. Organization Chart Encl ML20207G2171999-06-0707 June 1999 Forwards SE Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage for Plant,Unit 1 ML20195D5001999-06-0404 June 1999 Discusses NMPC Request That GE-NE-523-B13-01869-113, Assessment of Crack Growth Rates Applicable to Nine Mile Point I Vertical Indications, Rev 0 Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20207D3141999-05-28028 May 1999 Ack Receipt of 981203,990325 & 0415 Ltrs,Which Presented Several Concerns & Comments Re Operation of Nmp,Plant,Unit 1 During Last Operating Cycle ML20207E8131999-05-28028 May 1999 Responds to Re Concern for Core Shroud Insp Plan for Plant,Unit 1.Insp Results Cannot Be Made Available Before Plant Restarts ML20207A4881999-05-20020 May 1999 Discusses Expressing Concern Re Core Shroud at NMPNS Unit 1 & Indicating Desire to See Further Testing of Any Cracks & Release of Rept to Public Before Unit Restarted ML20207B0171999-05-18018 May 1999 Forwards Safety Evaluation Accepting Rept TR-107285, BWR Vessel & Internals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996 ML20206U5191999-05-17017 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Units 1 & 2 ML20206N6881999-05-12012 May 1999 Forwards Copy of NMP Ltr of 990430,responding to 990325 & 0415 Ltrs Re Core Shroud Evaluations for Plant Unit 1 ML20206M2041999-05-10010 May 1999 Requests Util Provide Written Comments to NRC Addressing Petitioners Expressed Concerns That Involve Licensee Activities.Petitioner Asserts That Util Actions Resulted in Placement of Confidential & Fraudulent Employee Evaluation ML20206K1681999-05-10010 May 1999 Forwards RAI Re 981116 Request for License Amend to Change TSs Re Implementation of Sys for Detection & Suppression of Coupled neutronic/thermal-hydraulic Instabilities in Reactor at Plant,Unit 1.Response Requested by 990621 ML20206L3981999-04-30030 April 1999 Responds to Requesting Addl Info to Either Respond to Apparent Violation,Or Prepare for Predecisional Enforcement Conference Re Apparent Violation of NRC Requirements Identified by OI in Rept 1-98-033 ML20205Q6471999-04-13013 April 1999 Discusses OI Report 1-1998-033.Purpose of Investigation Was to Determine Whether SRO Willfully Violated Conditions of SRO License by Assuming Assistant Station Shift Supervisor Position After Failing Requalification Scenario Evaluation ML20205N0591999-04-12012 April 1999 Forwards RAI Re Which Describes Proposed Core Shroud Repair for Core Shroud Vertical Welds at Plant,Unit 1.Response Requested by 990414 IA-99-179, Final Response to FOIA Request for Documents.App a Records Already Available in PDR1999-04-0808 April 1999 Final Response to FOIA Request for Documents.App a Records Already Available in PDR ML20205J3761999-04-0808 April 1999 Final Response to FOIA Request for Documents.App a Records Already Available in PDR ML20207L0111999-03-11011 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Nine Mile Point Nuclear Station,Units 1 & 2 ML20207L5711999-03-0404 March 1999 Informs That Info Submitted with 990203 Application Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR.790 & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20207K3701999-03-0303 March 1999 Forwards NRC PRB Meeting Summary Re Recipient Ltr of 981214, Expressing Concern for Degraded Core Shroud & Vessel Internals at Nine Mile Point Unit 1 ML20203E7281999-02-11011 February 1999 Responds to to W Travers & Submitted Pursuant to 10CFR2.206,requesting That NRC Convene Public Hearing to Consider Revocation of Operating License for Nine Mile Point Nuclear Station,Unit 1.Petition Does Not Meet Criteria ML20203B4671999-02-0808 February 1999 Informs That Licensee 990111 Application & Affidavit Submitting HI-961584,HI-971667,HI-92801 & HI-89330 Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20199E2701999-01-14014 January 1999 Ltr Contract:Mod 1 to Task Order 235, Review & Evaluation of Nine Mile 2 Nuclear Plant Application for Conversion to Improved TSs - Electrical Sys, Under Contract NRC-03-95-026 ML20206R8331999-01-14014 January 1999 Advises That, Licensing Rept for Reracking Nine Mile,Unit 1 Spent Fuel Pool, Will Be Withheld from Public Disclosure, Per 10CFR2.790 ML20206R6161999-01-12012 January 1999 Informs That on 981124 Licensee Submitted Revs to TSs Bases for Plant,Unit 1.Revs Update Listed Bases to Incorporate Design Changes Affecting Reactor Fuel,Reactor Vessel Water Level Instrumentation & Drywell Leak Detection Sys ML20199D2801999-01-12012 January 1999 Informs That on 981204,NMP Submitted Rev to TSs Bases for NMPNS Unit 1.Rev Update Bases for 3.6.2 & 4.6.2 Protective Instrumentation. Forwards Modified Pages for NMP Unit 1 TS Bases for Insertion Into TSs ML20206R0831999-01-0404 January 1999 Informs That Privacy Info Re Investigation Rept Entitled, Results of Independent Team Investigation of Concerns Involving Erosion & Corrosion of Flow Elements, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20198L1971998-12-24024 December 1998 Informs That Based Upon Conclusion That Current Design & Licensing Basis Does Not Credit Containment Overpressure to Ensure Adequate NPSH to Core Spray & Containment Spray Pumps,Nrc Considers GL 97-04 Closed Per 980807 RAI ML20198L3831998-12-23023 December 1998 Forwards Insp Repts 50-220/98-15 & 50-410/98-15 on 980927-1121.No Violations Noted.Notes Challenges Faced by Unit 2 Operators Due to Equipment Performance Problems 1999-09-30 |
Inspection Report - Nine Mile Point - 1983006 | |
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NAR 3 1986 Docket No. 50-410 Niagara Mohawk Power Corporation ATTN: Mr. B. G. Hooten Executive Director Nuclear Operations c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, New York 13202 Gentlemen:
Subject:
Inspection No. 83-06 This refers to your letter dated February 7,1986, in response to our letter dated August 7, 1985.
Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely, Origina1 Signed Ett.
Stewart D. Ebneter, Director Division of Reactor Safety cc:
Connor & Wetterhahn John W. Keib, Esquire D. Quamme, NMP-2 Project Director C. Beckham, NMPC QA Manager T. J. Perkins, General Superintendent R. B. Abbott, Station Superintendent Department of Public Service, State of New York Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York 0FFICIAL RECORD COPY RL NMP2 83-06 - 0001.0.0 t(
02/27/86 0603100360 060303
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Region I Docket Reom (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief J. Grant, DRP Region I SLO
RI:DRS RI:DRS Anderson Durr 02/n/86 02/.2 3186 ejq OFFICIAL RECORD COPY RL NMP2 83-06 - 0002.0.0 02/27/86
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NIACARA MOHAWK POWER C04PORATION/300 ERIE SOULEVAAo WEST. SYR ACUSE. N Y 13202/ TELEPHONE (315) 4741511 February 7, 1986 (NMP2L 0605)
Mr. R., Di rector U.S. Nuclear Regulatory Comission Region I f)ivision of Reactor Pmjects 631 Park Avenae
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King of Prussia, 7A 19406 Re:
Nine ftile Point Unit 2 i
Docket No. 50-410 l
Dear Mr. Starostecki:
The following is submi tted in response to your letter dated August 7, 1985 concerning the apparent violation identi fied in Inspec tion Report No.
50-410/83 06.
Subsequent to our response to the Nuclear Regul atory Comission on
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Septenber 26, 1983, the fianagerient Analysis Company i ndependent assessment
which was rev' ewing violations and discrepancies, issJed a Corrective temi,
Action P,equest with respect to the apparent violation identi fied in Inspection
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peport 83-06.
Niagara 'bhawk responded to the Corrective Action Request by i ndic ati ng th at an independent Fi nal Sa fety Analysis Peport veri fic ation l
program had been instituted to help ensure the accuracy of the Final Safety
I Analysis Peport at the time of licensing.
The fianaqccient Analysis Cmipany assessnent tean accepted the Niagara fichawk resolution of this Correc tive l
Action Request.
Since the initial discrepancy has been corrected, and Niagara !bhawk has instituted a specific proarri to help ensure the accuracy of the Final Safety Analysis Report, Niagara tbhawk does not believe that any further discussion rJgardi ng the interpretation of the apparent violation would enhanc e the resolution of this issue.
As we have discussed at several rieetings with your
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staff, the Final Safety Analysis Report veri fication progran has identifled a ntriber of changes which have been incorporated into the Final Safety Analysis R; port to reflec t the design of Unit 2 Fo r thi s rea so n, Niagara tthawk halieves that this issue can be resolved.
Very truly yours,
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C. V. fiangan
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Senior Vice President
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xc: nirector of Inspection and Enfortement U.S. Nuclear Regulatory Comission Wa shi ngton, ' DC 20555 R. A. Grav, NRC Senior Resident inspector Pr7 ject File (2)
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