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| {{Adams | | {{Adams |
| | number = ML20211A916 | | | number = ML20235G953 |
| | issue date = 02/04/1987 | | | issue date = 02/24/1987 |
| | title = 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 | | | title = Informs of Closeout of Allegation RI-86-A-0125.Region Findings Documented in Insp Rept 50-410/86-56 Dtd 861217. Allegation Unsubstantiated.B.Cook Feb 10 Memo Encl |
| | author name = Kane W | | | author name = Linville J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = Mangan C | | | addressee name = Shropshire A |
| | addressee affiliation = NIAGARA MOHAWK POWER CORP. | | | addressee affiliation = NRC |
| | docket = 05000410 | | | docket = 05000410 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = EA-87-009, EA-87-9, NUDOCS 8702190262 | | | case reference number = FOIA-87-438 |
| | package number = ML20211A920 | | | document report number = NUDOCS 8709300309 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | package number = ML20235G041 |
| | page count = 3 | | | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE |
| | | page count = 2 |
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| | 24 FEB 1987 |
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| 04 FEB 1987 Docket No. 50-410 License No. NPF-54 EA 87-09 Niagara Mohawk Power Corporation ATTN: Mr. C. V. Mangan Senior Vice President 301 Plainfield Road Syracuse, New York 13212 h Gentlemen:
| | MEMORANDUM FOR: lan Shropshire, Compliance and Allegation Assistant FROM: J. C. Linville, Chief, Reactor Projects Section 2C |
| Subject: NOTICE OF VIOLATION (Inspection No. 50-410/86-56)
| |
| This refers to the NRC resident safety inspection conducted between October 1 and November 16, 1986, at Nine Mile Point, Unit 2, Scriba, New York. The inspection report was sent to you on December 17, 1986. During the inspection, NRC inspectors reviewed the circumstances associated with two violations of '
| |
| technical specification limiting conditions for operation (LCO) which were identified by members of your staff and reported to the NRC. Further, a viola-tion of the reporting requirements set forth in 10 CFR 50.72 was also identi-fied. On January 8, 1987, an enforcement conference was conducted with you and members of your staff to discuss the violations, their causes, and your corrective action The two LCO violations occurred during the initial loading of fuel in the reactor. The first violation involved a Source Range Monitor being inoperable for approximately 5 hours during which time 19 fuel bundles were loaded into the reactor. The violation was caused by a failure to follow procedures and a lack of independent verification to assure that the SRM was returned to an operable status upon completion of a surveillance test. The second violation involved all four SRM downscale rod block channels being inoperable for a period of approximately 21s hours while the reactor was in the refueling mode (there was no fuel movement during that time). The violation was caused by an apparent lack of thorough understanding and implementation of technical speci-fication requirements. The violations demonstrate the need for additional training and improved oversight of the operations staff to assure that the plant is operated in accordance with the technical specificatior.s. Therefore, although the two LCO violations are of low safety significance and have been classified at Severity Level IV in accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy) (1986), we emphasize that any similar violations in the future may result in additional enforcement action. The reportin$ violation
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| , has been classified at Severity Level ON o$8lj{g PDR OFFICIAL RECORD COPY CP NMP2 - 0003.0.0 g 5 02/02/87 fhO
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| _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _
| | SUBJECTi CLOSE0VT OF ALLEGATION N0. RI-86-A-0125 AT NINE MILE POINT UNIT 2 This allegation is close The Region's findings are documented in Inspection Report No. 410/86-56 dated December 17, 198 The Region has determined this allegation to be unsubstantiate I have enclosed my file to complete your record ( , |
| . .
| | J. C. Linville/ Jr , Chief eactor Projde'ts Section 2C Enclosures: As stated cc: |
| Niagara Mohawk Power Corporation 2 04 FEl31987 You are required to respond to the enclosed Notice and, in preparing your response, you should follow the instructions specified in the Notic In your response, you should document the actions taken or planned to prevent recurrence. After reviewing your response to the Notice, including your proposed corrective actions and the results of future inspections, the NRC will determine whether further enforcement action is necessary to ensure compliance with NRC regulatory requirement In accordance with 10 CFR 2.790, a copy of this letter and its enclosure will be placed in the NRC Public Document Roo The responses directed by this letter and the enclosed Notice are not subject -
| | W. Cook I |
| to the clearance procedures of the Office of Management and Budget, otherwise required by the Paperwork Reduction Act of 1980, PL 96-51
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| | i Fez A-97- 43g 8709300309 870924 M4 |
| | -[TE., |
| | -438 PDR |
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| Sincerely, William F. Kane, Director Division of Reactor Projects Enclosure:
| | _ _ - _ _ . _, |
| Notice of Violation cc w/ encl:
| | ._ .__ |
| Connor & Wetterhahn John W. Keib, Esquire J. A. Perry, Vice President', Quality Assurance W. Hansen, Manager of Quality Assurance 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)
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| Local Public Document Room (LPDR)
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| Nuclear Safety Information Center (NSIC)
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| NRC Resident Inspector State of New York bec w/ encl:
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| Region I Docket Room (with concurrences)
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| Management Assistant, DRMA (w/o encl)
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| DRP Section Chief Region I SLO Robert J. Bores, DRSS D. Holody 0FFICIAL RECORD COPY CP NMP2 - 0003. /02/87 i
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217E1501999-10-0707 October 1999
Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station
ML20216F5061999-09-16016 September 1999
Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld
ML20210L6431999-08-0606 August 1999
Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen
ML20210C1631999-07-19019 July 1999
Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld
ML20195G6941999-06-0808 June 1999
Rev 1,rescheduling Notification of 990625 Licensee Meeting 99-32 in King of Prussia,Pa with Util to Discuss Recent Plant Initiatives to Improve Corrective Action Program & Processes
ML20195C5081999-06-0303 June 1999
Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods
ML20207F2701999-05-25025 May 1999
Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes
ML20206R3691999-05-0707 May 1999
Notification of Significant Licensee Meeting 99-24 with Util Current Employee on 990513 to Discuss Apparent Violation of 10CFR55,noted in NRC Correspondence to Individual Ref OI Rept 1-1998-033
ML20154D8211998-10-0505 October 1998
Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs
ML20151V1241998-09-0909 September 1998
Notification of 980924 Meeting W/Util & Public in Oswego,Ny to Review NMPC Request to Extend Current Core Shroud Vertical Weld Insp Interval & to Receive Comments/Questions Re NMPC Request to Extend Unit 1 Core Shroud Vertical Weld
IR 05000220/19980031998-08-20020 August 1998
Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution
ML20237C9501998-08-20020 August 1998
Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23
ML20236X5631998-07-31031 July 1998
Discusses NMP & Several Supporting Ltrs, Requesting That NRC Authorize Extension of Insp Interval for Cracks in Plant,Unit 1 Core Shroud Welds from 10,600 Hot Operating H to 14,500 Hot Operating H
ML20217F4411998-03-19019 March 1998
Forwards Order Approving Application Re Acquisition of New York State Electric & Gas Corp by Holding Co Affecting License NPF-69,Nine Mile Point Nuclear Station,Unit 2 for Fr Publication
ML20203A3041998-02-0606 February 1998
Notification of 980224 Meeting W/Niagara Mohawk Power Corp in Rockville,Md to Discuss Schedules for Current & Projected Licensing Actions & Licensing Activities for Project Mgt Purposes
ML20199C0771998-01-23023 January 1998
Corrected Notification of 980128 Meeting W/Nmp in Rockville, Md,To Disduss NRC Position That Exceeding Relief Pressures Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs Should Have Been Reported in 1993
ML20198J4911998-01-0606 January 1998
Notification of 980128 Meeting W/Nmp in Rockville,Md to Discuss NRC Position That Exceeding Relief Pressure Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs That Should Have Been Reported to NRC in 1993
ML20202B2321997-12-0101 December 1997
Responds to 960313 Memo Requesting NRR Technical Assistance to Determine Adequacy of NMPC Revised Design Calculations for Reactor Bldg & Turbine Bldg Pressure Relief (or Blowout) Panels.Partially Withheld
ML20217E8371997-10-0101 October 1997
Notification of 971009 Meeting W/Util in Rockville,Md to Discuss Mgt Aspects of Current & Pending Licensing Activities,Including Plans to Convert Unit 2 to Improved Std TSs Plans Re Unit 1 Core Shroud Insp & Associated Schedule
ML20202B1451997-09-24024 September 1997
Discusses Response to Nine Mile Point on Blow Out Panels
ML20199J0971997-08-21021 August 1997
Emails Info Re Plant Blowout Panels
ML20149F1531997-07-16016 July 1997
Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606
ML20199J1041997-07-0707 July 1997
Emails Util Ltr for concurrence,EA-96-079.Comments Requested
ML20202B1721997-07-0707 July 1997
Requests Concurrence on by 970714.Partially Withheld
ML20138C7071997-04-29029 April 1997
Forwards Summary for Two Public Meetings Held W/Nmp on 970414 to Discuss Core Shroud Issues at Plant,Unit 1.Copies of Subj Meeting Videotape Have Been Sent to PDR
ML20140C4811997-04-11011 April 1997
Discusses Exams of Core Shroud Welds & Tie Rod Repair Assemblies Conducted During Current Refueling Outage at Plant,Unit 1 & Initiation of Adjustments to One of Core Tie Rods
ML20137S3611997-04-0303 April 1997
Notification of Cancelled 970410 Meeting W/Util in Rockville Md,Rescheduled on 970414 in Oswego,Ny,To Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results That Revealed Cracks in Heat Affected Zones
ML20137L4441997-04-0303 April 1997
Notification of 970410 Meeting W/Util in Rockville,Md to Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results Revealing Cracks in Heat Affected Zones of Horizontal & Vertical Welds
ML20147H6501997-04-0101 April 1997
Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320
ML20136C1031997-03-0606 March 1997
Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR
ML20147D7251997-02-0707 February 1997
Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves
ML20133J4681997-01-13013 January 1997
Discusses 961114 AEOD Presentation of Assessment of Spent Fuel Cooling Viewgraph 13, Reduced Time to Boil at Nine Mile Point Unit 2, & Forwards Figures
ML20203J4821997-01-0303 January 1997
Forwards SE Re Reactor & Turbine Building blow-out Panels
IA-97-375, Forwards SE Re Reactor & Turbine Building blow-out Panels1997-01-0303 January 1997
Forwards SE Re Reactor & Turbine Building blow-out Panels
ML20203J4611997-01-0202 January 1997
Forwards SE Accepting Subj Panels as Modified & Supported by Discussed Engineering Analysis Results
ML20135C6361996-12-0404 December 1996
Forwards Signed Original of Order Imposing Monetary Penalty for Plant,Unit 1.W/o Encl
ML20129K2561996-11-0505 November 1996
Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness
ML20129J4781996-11-0404 November 1996
Summarizes 961030 Operating Reactors Events Briefing 96-14 Re Notification of Senior Managers from Commission,Oe,Aeod, Res,Nrr & Regional Offices of Selected Events That Occurred Since 961023 Briefing.List of Attendees Encl
ML20199J0911996-05-0101 May 1996
Requests Technical Assistance Supplement 1,in Determining If Util Interpretation Re Reactor & Turbine Bldgs Blowout Panels,Per 10CFR50.59 SE Requirements
ML20199J0841996-03-13013 March 1996
Submits Request for Technical Assistance to Determine Technical Adequacy of Util Revised Design Calculations for Reactor & Turbine Bldgs Blowout Panels
NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994
Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl
ML20056E4571993-08-0505 August 1993
Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant
IR 05000220/19860171989-05-24024 May 1989
Advises That Insp Rept 50-220/86-17 Re Installation of non-safety Grade Connectors Addresses Technical Significance of Allegations That Ellison Willfully Installed Uncertified Connectors.Civil Penalty of $50,000 Issued to Util
ML20245B6531989-04-15015 April 1989
Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys
ML20245B6421989-04-15015 April 1989
Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20245B6191989-04-15015 April 1989
Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both
ML20245B7501989-04-15015 April 1989
Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20246G9211989-02-24024 February 1989
Documents Info Re Ellison Background/Character Re Alleged Storage of Radioactive Matl in Home,Conviction for Sex Crimes & Trouble in Florida W/Girlfriend
IA-89-305, Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room1988-05-0202 May 1988
Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room
ML20247N5151988-05-0202 May 1988
Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room
1999-09-16
[Table view]
Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217E1501999-10-0707 October 1999
Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station
ML20216F5061999-09-16016 September 1999
Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld
ML20210L6431999-08-0606 August 1999
Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen
ML20210C1631999-07-19019 July 1999
Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld
ML20195G6941999-06-0808 June 1999
Rev 1,rescheduling Notification of 990625 Licensee Meeting 99-32 in King of Prussia,Pa with Util to Discuss Recent Plant Initiatives to Improve Corrective Action Program & Processes
ML20195C5081999-06-0303 June 1999
Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods
ML20207F2701999-05-25025 May 1999
Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes
ML20206R3691999-05-0707 May 1999
Notification of Significant Licensee Meeting 99-24 with Util Current Employee on 990513 to Discuss Apparent Violation of 10CFR55,noted in NRC Correspondence to Individual Ref OI Rept 1-1998-033
ML20154D8211998-10-0505 October 1998
Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs
ML20151V1241998-09-0909 September 1998
Notification of 980924 Meeting W/Util & Public in Oswego,Ny to Review NMPC Request to Extend Current Core Shroud Vertical Weld Insp Interval & to Receive Comments/Questions Re NMPC Request to Extend Unit 1 Core Shroud Vertical Weld
IR 05000220/19980031998-08-20020 August 1998
Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution
ML20237C9501998-08-20020 August 1998
Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23
ML20236X5631998-07-31031 July 1998
Discusses NMP & Several Supporting Ltrs, Requesting That NRC Authorize Extension of Insp Interval for Cracks in Plant,Unit 1 Core Shroud Welds from 10,600 Hot Operating H to 14,500 Hot Operating H
ML20217F4411998-03-19019 March 1998
Forwards Order Approving Application Re Acquisition of New York State Electric & Gas Corp by Holding Co Affecting License NPF-69,Nine Mile Point Nuclear Station,Unit 2 for Fr Publication
ML20203A3041998-02-0606 February 1998
Notification of 980224 Meeting W/Niagara Mohawk Power Corp in Rockville,Md to Discuss Schedules for Current & Projected Licensing Actions & Licensing Activities for Project Mgt Purposes
ML20199C0771998-01-23023 January 1998
Corrected Notification of 980128 Meeting W/Nmp in Rockville, Md,To Disduss NRC Position That Exceeding Relief Pressures Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs Should Have Been Reported in 1993
ML20198J4911998-01-0606 January 1998
Notification of 980128 Meeting W/Nmp in Rockville,Md to Discuss NRC Position That Exceeding Relief Pressure Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs That Should Have Been Reported to NRC in 1993
ML20202B2321997-12-0101 December 1997
Responds to 960313 Memo Requesting NRR Technical Assistance to Determine Adequacy of NMPC Revised Design Calculations for Reactor Bldg & Turbine Bldg Pressure Relief (or Blowout) Panels.Partially Withheld
ML20217E8371997-10-0101 October 1997
Notification of 971009 Meeting W/Util in Rockville,Md to Discuss Mgt Aspects of Current & Pending Licensing Activities,Including Plans to Convert Unit 2 to Improved Std TSs Plans Re Unit 1 Core Shroud Insp & Associated Schedule
ML20202B1451997-09-24024 September 1997
Discusses Response to Nine Mile Point on Blow Out Panels
ML20199J0971997-08-21021 August 1997
Emails Info Re Plant Blowout Panels
ML20149F1531997-07-16016 July 1997
Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606
ML20202B1721997-07-0707 July 1997
Requests Concurrence on by 970714.Partially Withheld
ML20199J1041997-07-0707 July 1997
Emails Util Ltr for concurrence,EA-96-079.Comments Requested
ML20138C7071997-04-29029 April 1997
Forwards Summary for Two Public Meetings Held W/Nmp on 970414 to Discuss Core Shroud Issues at Plant,Unit 1.Copies of Subj Meeting Videotape Have Been Sent to PDR
ML20140C4811997-04-11011 April 1997
Discusses Exams of Core Shroud Welds & Tie Rod Repair Assemblies Conducted During Current Refueling Outage at Plant,Unit 1 & Initiation of Adjustments to One of Core Tie Rods
ML20137S3611997-04-0303 April 1997
Notification of Cancelled 970410 Meeting W/Util in Rockville Md,Rescheduled on 970414 in Oswego,Ny,To Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results That Revealed Cracks in Heat Affected Zones
ML20137L4441997-04-0303 April 1997
Notification of 970410 Meeting W/Util in Rockville,Md to Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results Revealing Cracks in Heat Affected Zones of Horizontal & Vertical Welds
ML20147H6501997-04-0101 April 1997
Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320
ML20136C1031997-03-0606 March 1997
Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR
ML20147D7251997-02-0707 February 1997
Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves
ML20133J4681997-01-13013 January 1997
Discusses 961114 AEOD Presentation of Assessment of Spent Fuel Cooling Viewgraph 13, Reduced Time to Boil at Nine Mile Point Unit 2, & Forwards Figures
IA-97-375, Forwards SE Re Reactor & Turbine Building blow-out Panels1997-01-0303 January 1997
Forwards SE Re Reactor & Turbine Building blow-out Panels
ML20203J4821997-01-0303 January 1997
Forwards SE Re Reactor & Turbine Building blow-out Panels
ML20203J4611997-01-0202 January 1997
Forwards SE Accepting Subj Panels as Modified & Supported by Discussed Engineering Analysis Results
ML20135C6361996-12-0404 December 1996
Forwards Signed Original of Order Imposing Monetary Penalty for Plant,Unit 1.W/o Encl
ML20129K2561996-11-0505 November 1996
Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness
ML20129J4781996-11-0404 November 1996
Summarizes 961030 Operating Reactors Events Briefing 96-14 Re Notification of Senior Managers from Commission,Oe,Aeod, Res,Nrr & Regional Offices of Selected Events That Occurred Since 961023 Briefing.List of Attendees Encl
ML20199J0911996-05-0101 May 1996
Requests Technical Assistance Supplement 1,in Determining If Util Interpretation Re Reactor & Turbine Bldgs Blowout Panels,Per 10CFR50.59 SE Requirements
ML20199J0841996-03-13013 March 1996
Submits Request for Technical Assistance to Determine Technical Adequacy of Util Revised Design Calculations for Reactor & Turbine Bldgs Blowout Panels
NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994
Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl
ML20056E4571993-08-0505 August 1993
Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant
ML20245L5981989-08-17017 August 1989
Staff Requirements Memo on 890802 Briefing in Rockville,Md Re Status of Nine Mile Point Unit 1
IR 05000220/19860171989-05-24024 May 1989
Advises That Insp Rept 50-220/86-17 Re Installation of non-safety Grade Connectors Addresses Technical Significance of Allegations That Ellison Willfully Installed Uncertified Connectors.Civil Penalty of $50,000 Issued to Util
ML20245B7501989-04-15015 April 1989
Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20245B6191989-04-15015 April 1989
Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both
ML20245B6421989-04-15015 April 1989
Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart
ML20245B6531989-04-15015 April 1989
Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys
ML20246G9211989-02-24024 February 1989
Documents Info Re Ellison Background/Character Re Alleged Storage of Radioactive Matl in Home,Conviction for Sex Crimes & Trouble in Florida W/Girlfriend
IA-89-305, Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room1988-05-0202 May 1988
Forwards Ltr Received by Chairman Zech on 880428 Re Allegations of Drunk Employee in Control Room
1999-09-16
[Table view] |
Text
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24 FEB 1987
,
MEMORANDUM FOR: lan Shropshire, Compliance and Allegation Assistant FROM: J. C. Linville, Chief, Reactor Projects Section 2C
SUBJECTi CLOSE0VT OF ALLEGATION N0. RI-86-A-0125 AT NINE MILE POINT UNIT 2 This allegation is close The Region's findings are documented in Inspection Report No. 410/86-56 dated December 17, 198 The Region has determined this allegation to be unsubstantiate I have enclosed my file to complete your record ( ,
J. C. Linville/ Jr , Chief eactor Projde'ts Section 2C Enclosures: As stated cc:
W. Cook I
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