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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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h* ,,
SEP 131985 Docket No. 50-410 NOTE TO: Centr'al File .
FROM: . Mary F. Haughey, Project Manager Licensing Branch No. 2. ' -
Division of Licensing
SUBJECT:
CORRESPONDENCE BETWEEN THE NRC AND THE HAUPTABTEILUNG FUR DIE SICHERHEIT DER KERNANLAGEN CONCERNING THE USE OF GULF AND WESTERN-BALL VALVES AT THE LEIBSTADT NUCLEAR POWER STATION The enclosed information includes correspondence between the NRC and the Hauptabteilung fur die Sicherheit der Kernanlagen concerning the use of Gulf and.
Western Ball Valves at the Leibstadt Nuclear Power Station. These are the same valves that are used as Mainstream Isolation Valves (MSIV's) at Nine Mile Point 2.
The enclosed correspondence documents the operating history and problems with these valves at the Leibstadt Nuclear Power Plant in Switzerland. A copy of the May 23, 1985 report was made available to Niagara Mohawk Power Corporation for their information.
Mary F. Haughey, Project Manager Licensing Branch No. 2 !
Division of Licensing l l
Noted: Walter R. Butler ~
Enclosure:
As stated DISTRIBUTION Docket Fils LBf2 Reading PRC System MHaughey EHylton JRead PDR LPDR
% wL, LB#2/M7PN # LBf2/DL/LA LBf2/DL/BC Q MHaughey:mk EHylton WButler , _/
9/45 /85 9/ /85 9/ 85 W Fo2. A Y3F
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DISTRIBUTION AEB R/F d ->
h, OCT 2 61984 up s a.
\
Mr. F. Weehuizen . \
g Bundesamt fur die Energiewirtschaft Hauptabteilung fur die Sicherteit der Kernanlagen -
.5303 WURENLINGEN. Switzerland
Dear Mr. Weehuizen,
At a recent CSNI/GREST meeting I met Mr. G. Prohaska, who refe d me to you as the best contact for some information concerning the ss experience wi,'.h a' specific BWR main steam isolation valve (MS ). We are currently in the process of evaluating the potential for eakage of a new double-seat.MSIV for a U. S. plant for which no previ U. S.
experience exists. We understand that a similar valve is in talled at the Leibstatt BWR in Switzerland. Furthermore, we have heard that some difficulties were encountered in making these valves meet agp11 cable leakage criteria. I would appreciate any information conceening the pre-operational testing and operational experience with the MSIV's on the Leibstatt plant. If you can make the information available, our interest centers on: '
1 The leak rates encountered in pre-operational testing i{ Any additional test data foliowing start-up I-
- 3. Your assessment of the causes of leakage, particularly if
' excessive leakage was encountered
, .,, 4. Corrections or modifications, if any, to the valves to j improve performance. -
Your help with this issue will be much appreciated. ,
l Sincerely..
L ,-
Walter F. Pasedag / /
i Accident Evaluation Branch
. Division of Systems Integration
.1 LaFleur cc: .
454993675(vM-
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y J' e i Hauptabteilung for die Sicherheit der Kemanlagen Division Principale de la Securfte des installations Nucleelres
[' Divisione Principale de!!a Sicurezza degIllmplantl Nucleari .
c . sro wm ngen, 29. Mai 1985 '
P 056/993011 in, ,,,,, , Oct. 26, 1984 Hr. W.F. Pasedag v g;;y,;'*;g Accident Evaluation Branch Division of System Integration in, zcen.a United States Nuclear Regulatory Commission Washington DC 20555 i 74'. O BW/re ' '
Leibstadt ball-type valves Dear Mr. Pasedag; Last October you asked for specific information about the.Le'ibstadt ball-type valves, referring to our Mr. Prohaska.
Enclosed please find our report about the subject. If you need more information, please specify the points in question.
Sincerely, h&'
W.Br$ndli Division of Reactor Safety Enclosure SWISS FEDERAL NUCLEAR SAFETY DIVISION 2 copies of tiSK 12/240 E
e e
9
/
5<>n36W$
'/ j'{ May 03, 1985 HSK 12/240 Typ i Chor:hter;
,+-
Hauptabteilung for die Sicherheit der Kernanteeen klassihkotion:
f Divleton principale de la Securtti des Installetkms Nucleelten Technical Report ,
Diviolone principale per la Sicurene degillmplanti Nucleari seertwiter: visum:
5303 Warentingen W. BrEndli e Tel. ose s so2s sa F. Weehuizen /re M rrenki, te no, seemstand : ,, seite - 3 """'*
Leibstadt NPP ,
5 --
Experience with ball-valves in the main steam and feedwater lines I at Leibstadt Nuclear Power Station The nuclear power station Leibstadt, a GE BWR/6 plant with a Mark ,
III Containment, has 6 Energy Product Group shut-off valves located i in the steam tunnel. A 33" diameter ball-valve is mounted on each of the four main steamlines between the outer containment isolation valve and turbine building penetration. A 27" valve is siinilarly
- mounted on each feedwater line. Ball surfaces are of tungsten carbi-de with a stellite underlay.
z ,
.j The feedwater shut-off valves are closed during reactor shut-down, !
E enabling the' condensate and feedwater system to be purged through .
A the condensate polishing system. The shut-off valves on the main !
} steamlines act as an activity release barrier against post LOCA
.'i leakage through the main steam isolation valves.
t i The choice of this type of valve was dictated by the tight space re.
[ .quirements at the installed location, as well;as by the manufactu-
- ' rer's guarantees concerning leak tightness and seismic design. Other i known and proven valves would have needed too much space. (Shut-off
[ valves, in addition to the isolation valves, were not provided in g the original project.)
a l
Verteiler : NRC Washington Ablage :
4M%93G45& KA
- 2 -
4 During pre-operational tests failures and damage occurred on severa'i occasions:
On the 5th October 1982 one of, the two feedwater valves remained . leak tight during'a' pressure test only'up to 24 bar/341 pst. At about.25 bar/
356 psi a serious leakage occurred. During a later test of the same val-ve a leakage of about'220 kg/h was measured at only 6 bar/85 psi. When the displacement pump used for leak-testing was stopped, the. pressure in the volume (110 m3) being tested sank to 1 bar within 5 minutes. The
, other. valve remained leak tight up to 169,bar/2404 psi. The four valves on the main steam lines passed the leak rate test.
3 After testing all six valves were opened up. All showed evidence of- I interior corrosion. The sliding spools, which bear on the surfaces of the ball, showed circumferential wear on one side of the valve and nickeldepositionontheother(Seeappendix1,remarkA.)TEespring loading on the sleeves was reduced and a new seal (manufacturer " Titan")
was installed. The housing was ground-out cicumferentially to obtain more radial clearance for the spools.
On the flange for Jhe valve bonnet a part of the surface was machined and provided with a hard facing. The lantern rings on both upper and lo-wer bearings were turned down. The self-sealing closure was dam, aged on the sealing surface in contact with the pressure seal. This surface also received a hard facing. The metallic sealing rings were replaced by seals of a softer material (remark B).
The thin tungsten carbide surface of the valve ball showed damage due to broken-out pieces in some areas. As a result of the damage, a review of the matching of ball and seat materials was undertaken by Prof. Grosch at the Technical University, Berlin. He expected more problems in the future from loss of the hard-metal layer. .
/
4 e
____.__._____._m_-. . _ _
O
. 3 .
- 'In the spring of 1983 problems with the valve drive mechanism' arose. Du-ring closure of one valve on the main steamline plastic deformation of the frame assembly occurred. These valves are closed by spring-force and
- are jacked open hydraulically,. The frames on all valves Nre strengthened.
The pump and motor of the electrohydraulic control crf the affected valve were replaced. Improvements to the hydraulic parts of the solenoid con-trol valves were intiroduced. On all the m6in steamline valves the drive for manually tripping the valves closed was replaced. On one valve the main hydraulic cylinder was replaced twice, once because the drive
% spindle was bent and then when the cylinder was scored.
lm With all these problems, repairs and changes the management lost conff-dence in the reliability of the valves.
- In summer 1985 the H5K allowed KKL to replace the feedwater valves by non-return valves of the type already used for containment isolation in these lines. Wedged-plate slide-valves mounted at the upstream end of I
, 'the lines in the turbine building now enable purging to be carried out through the condensate polishing system without involving the' primary system.
e No similar solution was available for the main steamlines, so the four ~
large ball-valves will remain in operation. Duri'ng normal reactor opera-tion.they will remain open. They will be tested only during the annual shutdown, when the lines are cold and not under pressure, j 3
KKL has still the intention to propose other solutions, but only after ,
I experience about the behaviour of the valves .in operation, and data con-cerning the leak-tightness of the inner and outer containment isolation valves, has been gathered over a period of several yoers.
To sumarize, the ball-valves and their operators in Leibstadt have had se-ver,e.and repeated problems. A solution has been found for the feedwater :li-nes by means of non-return and slide valves. In the long term the manage-ment hopes to be able to change to another type of valve on the main steam- )
l lines.
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