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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
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1 MEMORANDUM TO: Charles W. Hehl, Director Division of Reactor Projects, Region i FROM: Bruce E Boger, Director Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
SUBJECT:
TECHNICAL ASSISTANCE REQUEST REGARDING REACTOR AND TURBINE BUILDING RELIEF PANEL DEFICIENCY, NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (TAC NO. M94858)
By memorandum dated March 13,1996, DRP requested NRR technical assistance to determine the adequacy of Niagara Mohawk Power Corporation's (NMPC) revised design calcula' ions for the Reactor Building and Turbine Building pressure relief (or " blowout") panels.
The cc;culations are related to an event (LER 50-220/95-05, dated November 30,1995) regarding the licensee's discovery, in October 1993, that the panels would not blow out at the design pressure of 45 psf because the bolt fasteners for the panels were larger, and had a higher ultimate strength, than designed. The licensee's initial 1993 engineering calculation of this condition erroneously determined that the Turbine Building panels and Reactor Building panels would blow out at 60 and 53 psi, respectively, to relieve intemal building pressure prior l to structural failure of the buildings, and the panels were declared operable However, during a refueling outage in March 1995, the licensee discovered that an error had been made in 1993 regaroing the design ec&umotion for load distribution The licensee's revised 1995 calculations determined that the relief paneb would not blow out until the intemal building pressuro l
exceeded the minimun documented building structural design of 80 psf. Based on these calculations and before restarting Unit 1 in 1995, the licensee reported the condition to the NRC I and removed every other bolt from the panels to reduce their blowcut point to a value below the l
i documented building structural capability.
! By memorandum dated May 1,1996, Region i supplemented the request for technical l assistance to include two items arising from the related violations of EA 96-079 One item asked whether NMPC was correct in its 10 CFR 50.59 interpretation (apparently based on i
NSAC-125) that safety margins were not reduced because the actual blowout value (if not in j
error, which it was) was still under 80 psf The second item asked whether a 10 CFR 50.59 safety evaluation is needed before maning changes to restore a commitment or safety condition l
' consistent with the original intent of a design. In add, tion, with respect to a public meeting with the licensee on January 6,1997, Region I requested NRR support regarding the reportability of the panels being outside of their design basis.
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9712030079 971201 +
PDR FOIA WILLI APf97-373 PDR ,
6sleausev of Licensee's Calculatigna The licensee's 1993 and 1995 engineering calculations involving the Reactor Building blowout panels and Turbine Building blowout panels have been reviewed by NRR's Mechanical Engineering Branch (EMEB) and Civil Engineering and Geosciences Branch (ECGB). NRR's Containment Systems and Severe Accident Branch (SCSB) provioed technical support to EMEB and ECGB for this review. The pincipal reviewers were David Jeng (ECGB), Mark Hartzman (EMEB), and William Long (SCSB).
Enclosures 1 and 2 are the safety evaluations by ECGB and EMEB, respectively, in these SEs, the staff verified that the licensee's 1993 calculations were technically inadequate. The staff also found tha, the subsequent 1995 calculations, that were intended to correct the deficiencies in the 1993 calculations, were also technically inadequate. After several discussions with the licensee and revised submittals by the licensee to correct technicai deficiencies, the ECGB at:d EMEB reviewers conducted a site audit of the calculations and performed a walk down of the panels. After additional submittals by the licensee resolved issues raised by the NRC during the audit, the NRC staff concluded that the revised calculations were technically adequate.
Using the accepted methodology, the upper bound blowout pressure was determined to be 65 psf fer the Reactor Building panels with every other bolt removed (or 128 psf before the bolts were removed), and 62 psf for the Turbine Building panels after every other bolt was removed (or 122 pr.f before the bolts were removed). The revised ultimate lower bound cr.pacity of the Reactor Building was 117 psf while the corresponding capacity for the Turbine Building was 135 psf. The staff concludes in the SEs that there is ample safety margin for pressure relief of the buildings, based on the current number and size of the bolts.
The above results also show that before every other bol' was removed in 1995, the Reactor Building panels might not have contribuited to the overpressure protection of the Reactor Building (i.e., the panel's mar.imum blowout pressure exceeded the building's lower-bound ultimate capacity), and that the margin of saiety for the Turbine Building during this time was only 13 psf (135 psf minus 122 psf)-significantly less than the 35 psf or more (80 psf or more minus 45 psf) intended by the original design. j 10 CFR 5.0 59 ansi Renortability issues MW. ) Q$ / l SA be.ek At
\ \7/ Gg The NRC's position regarding NMPC's contention that the design bases for intemal building pressure is only to provide pressure relief at or below 80 psf is addressed in Mr. A. Thadani's letter to NMPC dated August XX,1997. As stated in that letter, the NRC considers that the blowout panel pressure of 45 psf is part of the design bases, that 45 psf established the reference for the acceptability of the facility's design, and exceeding 45 psf met the reporting requirements of both 10 CFR 50,72(2)(ii)(B) and 10 CFR 50.73(2)(ii)(B).
Because the NRC's position on the NMP1 violations was not based upon the " margin of safety" test specified in 1C OFR 50.59, the NMP1 citations will not be affected by the resolution of existing differences between industry and NRC as to the pmper definition of this term. By the NRC staff's definition, the margin of safety calculated in 1993 (i.e.,80 psf minus 60 or 53 psf) would be considered significantly less than the design basis margin (80 psf minus 45 psf).
Facility (or procedure) changes by licensees that merely restore a commitment or safety
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condition consistent with the intended design "as described in the safety analysis report" would not noimally require a 10 CFR 50.59 safety evaluation or prior Commission approval. For
. example, NMPC's action in 1995 of removing every other bolt from the panels to restore the blowout pressure to the FSAR specified value of 45 psf did not change the FSAR design description that the NRC staff found acceptable during the operating license review, and did not require a TS change; therefore, it did not require a 10 CFR 50.59 evaluation. The relevant requirements for such restorations are based upon the requirements for the intended design, including as applicable, the quality assurance criteria of 10 CFR 50, Appendix 8.
Enclosure 3 is a bibliogrepy of the principat documents aLociated with this technical review.
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This completes our efforts under TAC M94858 which is now closed.
i Docket No.f 66-220 :
Enclosures:
- 1. ECGB SE
~ 2. EMEB SE . >
=. 3. Bibliography cc w/ encl:- See next page ,
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DISTRIBUTION:
A. Dromerick T. Harris (e-mail only TLH3)
Docket File PUBLIC S. Little OGC
,oDI 1 R/F D. Hood ACRS S. Varga S West C. Cowgill, Region i G. Bagchi M. Hartzman D.Jeng R. Rothman R. Wessman L. Doerflein, Region i K. Manoly T.Liu E. McKenna M. Satorius DOCUMENT NAME: G:\NMPl\TIA To receive a copy of thic doctment, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment /enclor 'e T - No copy orrlu Pn:PDI 1 l Ej LAtPDI-1 l OtPDI 1 l l NAME DMood SLittle ADr eerick
<Date> <Date> <Date> 06/ /97
<Date>
Official Re:ord Copy 1
l
! PDI-1 DOCUMENT COVER PAGE l
DOCUMENT NAME: G:\NMPl\TIA ORIGINATOR: D. Hood SECRETARY: R. Laskin
SUBJECT:
TECHNICAL ASSISTANCE REQUEST REGARDING REACTOR AND TURDINE BUILDING RELIEF PANEL DEFICIENCY, NINE MILE P0 INT NUCLEAR STATION UNIT NO. 1 (TAC NO. M94858)
lBME PAIE
- 1. / /97
- 2. D Hood / /97
- 3. S Little / /97
- 4. A. Dromerick -
/ /97
- 5. / /97
- 6. / /97
- 7. Secretary - Dispatch PLEASE DO NOT REMOVE W IS SHEET FROM PACKAGE
- CAN THi.S DOCUMENT BE DELETED AFTER DISPATCH 7 YES , NO
1 BIBLIOGRAPHY
- 1. Final Safety Analysis Report, Nine Mile Point Nuclear Station (Unit 1), dated June 1967, including Section Ill.A.1.2," Turbine Building Design Bases -
Pressure Relief Design," and Section VI.B.1.2," Reactor Building - Design Gasis Pressure Rc!t:f Design."
- 2. Nuclear Safety Analysis Center report NSAC-125, " Guidelines for 10 CFR 60.59 Safety Evaluations,' datoc June 1989.
- 3. NRC Generic Letter 91-18 "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Non-Conforming Conditions and on Operability," dated November 7,1991, including two enclosures from NRC Inspection Manual Chapter 9900, " Technical Guidance."
Enclosure 1 is titled " Resolution of Degraded and Nonconforming Conditions,"
and Enclosure 2 is titled " Operable / Operability: Ensuring the Functional Capability of a System or Component."
- 4. NUREG-1022, Revision 1 Second Draft,
- Event Reporting Guidelines 10 CFR 50.7' x.150.73," dated February 1994.
5 Updated Final Safety Analysis Re, ort, Nine Mile Point Nuclear Station, Unit 1, dated June 1990, including Section Ill.A.1.2," Turbine Building - Design Bases
- Pressure Ralief Decign," and Section VI.C.1.2, " Reactor Building - Design Bases - Pressure Relief Design."
- 6. Letter f.om Niagcra Mohawk Power Corporation to U.S. NRC (NMP1L 1007),
dated November 30,1995, forwarding Unit i Licensee Event Report 95-005,
" Building Blowout Panels Outside the Design Basis Because of Construction Error." .
- 7. Mcr..orandum from Region 1 to NRR dated March 13,1996," Request for Technical Ast! stance on Nine Mile Point 1 Reactor and Turbine Building Blowout Panelt."
- 8. Letter from U.S. NRC to Niagara Mohawk Power Corporation, dated March 29,1996, forwarding (1) NRC Special Inspection Report Mo. 50-220/96-05; 50 410/96-05. (2) NRC staff questions, and (3)Section V of Enforcement Policy.
- 9. Memorandem from Region i dated April 2,1996," Notice of Significant Meeting," announcing enforcement conference with Niagara Mohawk Powei Cmoration scheduled for April 12,1996, in King of Prussia, Philadelphia.
i 10. Memorandum from Region 1 to NRR datad May 1,1996, " Request for Technical Assistance on Nine Mile Point 1 Reactor and Turbine Building Blowout Panels Supplement 1."
q 996, " Summary of
- 11. uemoraneum by D. Hood, U.S. NRC, dated Mm
1 I
Telephone Conversation of May 2,1996, on Reactor and Turbine Building Blowout Panels."
- 12. Memorandum by D. Hood, U.S. NRC, dated June 7,1996, " Summary of
- Telephone Conversation of May 22,1996, on Reactor and Turbine Building Blowout Panels."
Enclosure 3
t I
- 13. Letter from U.S. NRC to Niagara Mohawk Power Corpuration, dated June 18, !
1996," Notice of Violation and Proposed imposition of Civil Penalty $50,000,"
(EA C6-079).
- 14. Letter i c m Niagara Mohawk Power Corporation to U.S. NRC (NMPIL 1089),
dated une 26,1996, forwarding Supplement 1 to LER 95-05,
- Building Blowout Panels Outside Design Basis Because of Construction Error."
- 15. Letter from Niagara Mohawk Power Corporation to U.S. NRC (NMP1L 1096),
dated July 1,1996, Response to Questions in Enclosure .? of Inspection Report 50 220/96-05." 1
- 16. Letter from Niagara Mohawk Power Corporation to U.S. NRC (NMP1L 1100).
dated July 18,1996, replyirig to June 18,1999 Notice of Violation.
- 17. Memorandum by D. Hood, U.S. NRC, dated October 7,1996," Trip Report :
Regarding August 20,1996, Audit of Reactor and Turbine Building Blowout Panel Calculations." t
- 18. Memorandum by D. Hood, U.S. NRC, dated November 13,1996, " Summary ,
of Telephone Conversation of October 23,1996, on Reactor and Turbine Building Blowout Pan 31s."
- 19. Letter from Niagara Mohawk Power Corporation to U.S. NRC (NMP1L 1155),
dated November 15,1996, " Response to Trip Report for August 20,1996 Audit of Reactor and Turbine Building Blowout Ptnels."
- 20. Letter from U.S. NRC to Aiagara Mohawk Power Corporation, dated December 3,1996, " Order imposing a Civil Monetary Penalty - $50,000," (EA 96 079).
- 21. Memorandum by D. Hood, U.S. NRC, dated January 6,1997," Summary of Telephone Conversation of December 18,1996, on Reactor and Turbine Building Blowout Panels."
- 22. Letter from Niagara Mohawk Power Corporation to U.S. NRC (NMP1L 1177),
dated January 23,1997," Remittance of Civil, Penalty EA 96-079."
- 23. Letter frorn U.S. NRC to Niagara Mohawk Power Corporation, dated February 13,1997, 'orwarding a transcript and slides on the January 6,1997, public meeting to discuss issues associated with NRC enforcement action EA ,96-079.
- 24. Letter from N. Reynolds of Winston and Strawn (Counsel for Niagara Mohawk Power Corporation) to U.S. NRC, dated February 19,1997, requesting -
clarification of reporting requirerr,ents.
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- 25. NUREG-1606,
- Proposed Regulatory Guidance Related to implementation of 10 CFR 50.59 (Changes, Tests, or Experiments)," published as a draft report for comments April 1997. See e g., Section Ill.S. " Definition of Reduction in Margin of Safety."
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- 26. Memorandum from R. Zimmerman, U.S. NRC, to ADPR Project Manag( ,
and ADPR Project Directors, dated July 22,1997, " Interim Expectations Rc lated to Oversight of 10 CFR 50.59 Process and FSAR Updates."
- 27. Letter from A. Thadani, U.S. NRC, to Niagara Mohawk Power Corporation,
'1 dated August XX,1997, responding to request for clarification of reporting 4
requirements.
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