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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217D1001999-09-24024 September 1999 Summary of 990901 Meeting with Nmpc,Nyseg & Amergen Energy Co in Rockville,Maryland Re NMPC Plans & Pending Submittal Re Transfer of NMPC Interest & Authorities Under Operating Licenses for Nine Mile Point ML20207K3831998-12-31031 December 1998 Summary of 981218 PRB Meeting Re 2.206 Petition Request from P Gunter to W Travers,Nrc Requesting That NRC Convene Public Hearing to Consider Revocation of Nine Mile Point,Unit 1 Operating License ML20203H2091998-02-24024 February 1998 Summary of 980211 Telcon W/Niagara Mohawk Power Corp on Licensee Progress in Responding to NRC Request for Addl Info Requested During 970822 Telcon Re Licensee Application for License Amend to Change Rc Chemistry Requirements in TSs ML20141H9231997-05-20020 May 1997 Summary of 970516 Telcon W/Niagara Mohawk Power Corp Re Licensee Plans for non-code Repair to Reactor Water Cleanup Sys Piping at Nine Mile Point Nuclear Station 1. List of Participants & Info Submitted by Licensee Encl ML20137Z4011997-04-18018 April 1997 Summary of 970410-11 Telcon W/Util Re Licensee on Core Shroud Welds & Tie Rod Assemblies for Plant ML20147J1271997-04-0707 April 1997 Summary of Telcon on 970403 W/Nmpc to Discuss Licensees Observations from Insp of Weld 32-WD-050 Between Recirculation Sys Suction Piping & Isolation Valve 32-376 at Plant ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20196B9821988-12-0101 December 1988 Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl ML20214P8971986-11-25025 November 1986 Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20207L9571986-11-18018 November 1986 Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl IA-86-855, Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl1986-11-18018 November 1986 Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20140G0761986-01-31031 January 1986 Summary of 860124 Meeting W/Consultants to Discuss Adequacy of Downcomer Design in Context of Reanalysis Performed by Util.Design Marginal.Recommends Granting OL W/Listed Condition.List of Attendees Encl ML20141E9501985-11-18018 November 1985 Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl ML20136J5351985-08-0909 August 1985 Summary of 850805 Meeting W/Util & S&W in Bethesda,Md Re Preservice & Inservice Insp Programs ML20128N4771985-05-22022 May 1985 Summary of Operating Reactors Events 850515 Meeting.Div Directors or Representatives Briefed on Events Occurring Since 850507 Meeting.Assignment of Followup Review Responsibilities Discussed.Attendance List Encl ML20127M5991985-05-0101 May 1985 Summary of ACRS Subcommittee 850220-21 Meetings w/util,C-E & S&W in Syracuse,Ny Re Application for License.Schedule of meeting,sign-in Sheets of Attendees & List of Meeting Handouts Encl ML20148C1311979-12-20020 December 1979 Summary of Meeting W/Mark II Owners Group in Bethesda,Md Re Status of Several long-term Program Tasks in Advance of Final Documentation.Agenda,List of Attendees & Viewgraphs Encl ML20213D0331979-08-22022 August 1979 Summary of 790717-18 Meeting W/Mark II Owners Group Re long-term Program Tasks ML20213C8911979-03-14014 March 1979 Summary of 790213-14 Meeting W/Mark II Owners Group Re Lead Plant Acceptance Criteria & Intermediate Plant Program Tasks ML20150C6821978-11-13013 November 1978 Agenda for 781128-30 ACRS Meeting in San Francisco of Fluid Hydraulic Dynamic Effects Subcomm Re Mark II LOCA & SRV Pool Dynamic Loads & Load Combinations ML20062A9741978-10-0505 October 1978 Summary of 780921 Meeting Re Proposed Installation of Radwaste Incinerator at Facility.Agenda Encl ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan ML20127A4681978-03-0101 March 1978 Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl ML20214G8711978-01-11011 January 1978 Summary of 771202 Meeting W/Ge Re Rev 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. List of Meeting Attendees Encl ML20214G8691978-01-10010 January 1978 Summary of 770518-19 Meetings W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads Program ML20214G8451977-12-0202 December 1977 Summary of 770510 Meeting W/Mark II Owners Executive Committee Re Mark II Containment Dynamic Loads Program.List of Attendees & Viewgraphs Encl ML20214G8351977-11-29029 November 1977 Summary of 770401 & 0707 Meetings W/Mark II Owners & GE Re Methods for Combining Dynamic Loads for Structural Design of Mark II Containment.List of Attendees & Viewgraphs Encl ML20214G7951977-08-0202 August 1977 Summary of 770729 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Load Program ML20214G7841977-06-23023 June 1977 Summary of 770615 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Loads.List of Attendees Encl ML20214G7741977-06-0808 June 1977 Summary of 770526 Meeting W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads.List of Meeting Attendees Encl ML20141N3471977-05-20020 May 1977 Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl ML20214G6951977-04-18018 April 1977 Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl ML20214G4271976-12-29029 December 1976 Summary of 761202 Meeting W/Mark II Owners & GE Re Mark II Containment Structural Design & Pool Dynamic Loads Supporting Program.Attendee List & Viewgraphs Encl ML20214G4371976-12-0707 December 1976 Summary of 761027-28 Meetings W/Mark II Owners,Ge & BNL Re Pool Dynamic Loads Analytical Model & Test Program.Lists of Attendees & Viewgraphs Encl ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks ML20125C5721976-09-0909 September 1976 Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl ML20125D6581976-08-18018 August 1976 Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept ML20214G4501976-06-0808 June 1976 Summary of 760429 Meeting W/Ge,Mark II Owners & Respective Aes Re GE 751105 Design Basis Document NEDE-21061, Mark II Containment Dynamic Forcing Function Info Rept (Dffr) ML20214G6031975-08-26026 August 1975 Summary of 750821 Meeting W/Mark II Owners,Sargent & Lundy, Bechtel,S&W & B&R in Bethesda,Md Re Load Factors & Load Combinations for Assessing Capability of Mark II Containments to Accommodate Safety/Relief Valve Loads ML20235E9641975-08-0606 August 1975 Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl ML20214G7791975-07-0303 July 1975 Summary of 750630 Meeting W/Mark II Owners,Aes & GE in Bethesda,Md Re Role of Mark II Owners,Status of Const of Various Mark II Units & Program for Determining Mark II LOCA & Safety/Relief Valve Loads 1999-09-24
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217D1001999-09-24024 September 1999 Summary of 990901 Meeting with Nmpc,Nyseg & Amergen Energy Co in Rockville,Maryland Re NMPC Plans & Pending Submittal Re Transfer of NMPC Interest & Authorities Under Operating Licenses for Nine Mile Point ML20207K3831998-12-31031 December 1998 Summary of 981218 PRB Meeting Re 2.206 Petition Request from P Gunter to W Travers,Nrc Requesting That NRC Convene Public Hearing to Consider Revocation of Nine Mile Point,Unit 1 Operating License ML20203H2091998-02-24024 February 1998 Summary of 980211 Telcon W/Niagara Mohawk Power Corp on Licensee Progress in Responding to NRC Request for Addl Info Requested During 970822 Telcon Re Licensee Application for License Amend to Change Rc Chemistry Requirements in TSs ML20141H9231997-05-20020 May 1997 Summary of 970516 Telcon W/Niagara Mohawk Power Corp Re Licensee Plans for non-code Repair to Reactor Water Cleanup Sys Piping at Nine Mile Point Nuclear Station 1. List of Participants & Info Submitted by Licensee Encl ML20137Z4011997-04-18018 April 1997 Summary of 970410-11 Telcon W/Util Re Licensee on Core Shroud Welds & Tie Rod Assemblies for Plant ML20147J1271997-04-0707 April 1997 Summary of Telcon on 970403 W/Nmpc to Discuss Licensees Observations from Insp of Weld 32-WD-050 Between Recirculation Sys Suction Piping & Isolation Valve 32-376 at Plant ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20196B9821988-12-0101 December 1988 Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl ML20214P8971986-11-25025 November 1986 Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20207L9571986-11-18018 November 1986 Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl IA-86-855, Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl1986-11-18018 November 1986 Summary of 860909 Meeting W/Utils Re Improving Lines of Communication Between NRC & Licensees,Including Sholly Process,Interpretation of 10CFR50.59,Tech Spec Improvement Program & Discretionary Enforcement.Related Info Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20140G0761986-01-31031 January 1986 Summary of 860124 Meeting W/Consultants to Discuss Adequacy of Downcomer Design in Context of Reanalysis Performed by Util.Design Marginal.Recommends Granting OL W/Listed Condition.List of Attendees Encl ML20141E9501985-11-18018 November 1985 Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl ML20136J5351985-08-0909 August 1985 Summary of 850805 Meeting W/Util & S&W in Bethesda,Md Re Preservice & Inservice Insp Programs ML20128N4771985-05-22022 May 1985 Summary of Operating Reactors Events 850515 Meeting.Div Directors or Representatives Briefed on Events Occurring Since 850507 Meeting.Assignment of Followup Review Responsibilities Discussed.Attendance List Encl ML20127M5991985-05-0101 May 1985 Summary of ACRS Subcommittee 850220-21 Meetings w/util,C-E & S&W in Syracuse,Ny Re Application for License.Schedule of meeting,sign-in Sheets of Attendees & List of Meeting Handouts Encl ML20148C1311979-12-20020 December 1979 Summary of Meeting W/Mark II Owners Group in Bethesda,Md Re Status of Several long-term Program Tasks in Advance of Final Documentation.Agenda,List of Attendees & Viewgraphs Encl ML20213D0331979-08-22022 August 1979 Summary of 790717-18 Meeting W/Mark II Owners Group Re long-term Program Tasks ML20213C8911979-03-14014 March 1979 Summary of 790213-14 Meeting W/Mark II Owners Group Re Lead Plant Acceptance Criteria & Intermediate Plant Program Tasks ML20062A9741978-10-0505 October 1978 Summary of 780921 Meeting Re Proposed Installation of Radwaste Incinerator at Facility.Agenda Encl ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan ML20127A4681978-03-0101 March 1978 Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl ML20214G8711978-01-11011 January 1978 Summary of 771202 Meeting W/Ge Re Rev 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. List of Meeting Attendees Encl ML20214G8691978-01-10010 January 1978 Summary of 770518-19 Meetings W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads Program ML20214G8451977-12-0202 December 1977 Summary of 770510 Meeting W/Mark II Owners Executive Committee Re Mark II Containment Dynamic Loads Program.List of Attendees & Viewgraphs Encl ML20214G8351977-11-29029 November 1977 Summary of 770401 & 0707 Meetings W/Mark II Owners & GE Re Methods for Combining Dynamic Loads for Structural Design of Mark II Containment.List of Attendees & Viewgraphs Encl ML20214G7951977-08-0202 August 1977 Summary of 770729 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Load Program ML20214G7841977-06-23023 June 1977 Summary of 770615 Meeting W/Utils & GE Re Mark II Containment Pool Dynamic Loads.List of Attendees Encl ML20214G7741977-06-0808 June 1977 Summary of 770526 Meeting W/Mark II Owners & GE Re Mark II Containment Pool Dynamic Loads.List of Meeting Attendees Encl ML20141N3471977-05-20020 May 1977 Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl ML20214G6951977-04-18018 April 1977 Summary of 770216-17 Meeting W/Mark II Owners,Ge & BNL Re Mark II Containment Pool Dynamic Load Support Program.List of Meeting Attendees & Viewgraphs Encl ML20214G4271976-12-29029 December 1976 Summary of 761202 Meeting W/Mark II Owners & GE Re Mark II Containment Structural Design & Pool Dynamic Loads Supporting Program.Attendee List & Viewgraphs Encl ML20214G4371976-12-0707 December 1976 Summary of 761027-28 Meetings W/Mark II Owners,Ge & BNL Re Pool Dynamic Loads Analytical Model & Test Program.Lists of Attendees & Viewgraphs Encl ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks ML20125C5721976-09-0909 September 1976 Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl ML20125D6581976-08-18018 August 1976 Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept ML20214G4501976-06-0808 June 1976 Summary of 760429 Meeting W/Ge,Mark II Owners & Respective Aes Re GE 751105 Design Basis Document NEDE-21061, Mark II Containment Dynamic Forcing Function Info Rept (Dffr) ML20214G6031975-08-26026 August 1975 Summary of 750821 Meeting W/Mark II Owners,Sargent & Lundy, Bechtel,S&W & B&R in Bethesda,Md Re Load Factors & Load Combinations for Assessing Capability of Mark II Containments to Accommodate Safety/Relief Valve Loads ML20235E9641975-08-0606 August 1975 Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl ML20214G7791975-07-0303 July 1975 Summary of 750630 Meeting W/Mark II Owners,Aes & GE in Bethesda,Md Re Role of Mark II Owners,Status of Const of Various Mark II Units & Program for Determining Mark II LOCA & Safety/Relief Valve Loads 1999-09-24
[Table view] |
Text
. . - -- . . .. . - -- . _ - . - . - . . -, .
p ME49
[ \ UNITED STATES g j 2
NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 20066-4001 May 20, 1997 g . . . . . j#
LICENSEE: Niagara Mohawk Power Corporation .[# #
FACILITY: Nine Mile Point Nuclear Station, Unit No. I j
SUBJECT:
SUMMARY
OF TELEPHONE CONVERSATION OF MAY 16, 1997, ON NON-CODE
" REPAIRS OF NON-SAFETY RELATED REACTOR WATER CLEANUP SYSTEM WELD (TAC NO. M72442)
On May 16, 1997, the NRC staff participated in a telephone conference call 4
with Niagara Mohawk Power Corporation (NMPC) to discuss the licensee's plans ,
for a non-Code repair to the reactor water cleanup system (RWCU) piping at '
j Nine Mile Point Nuclear Station, No.1 (NMP-1). Participants are listed in Enclosure 1. Enclosure 2, which includes the information submitted by the licensee, was faxed to the NRC by the licensee prior to the telephone conference call.
BACKGROUND On the evening of May 15th, NMP-1 was shut down to repair a through-wall leak in the RWCU piping at the 33-FW-22 weld (isoable non-ASME Code, non-safety-related piping). Due to commitments made by NMP-1 in their Generic Letter (GL) 88-01 program, which includes this weld, they submitted all the relevant information that was available at the time to the NRC Project Manager. NMP-1 submitted that information so that they could receive approval on their proposed repair, which they needed before they would be allowed to restart.
NMPC also hired a consultant, MPR Associates, to assist with any analyses and evaluntions that might have been needed. These analyses and evaluations will be sLbmitted for NRC staff review. However, it should be noted that they are not required by NRC regulations.
DISCUSSION The repair proposed was a weld overlay on a weld that contains a through-wall flaw (pinhole leak) in the stainless steel portion of a bi-metallic weld.
This weld is in a portion of the RWCU piping that is non-safety related, 1 isolable, and is not ASME Code Class piping. The leak was suspected during previous operation, but could not be located. Upon the latest startup, during which main turbine imbalances were addressed, the leak was located and the .
plant shut down to address this problem. l The conference call was held at 1:30 p.m. EST to discuss the proposed repair of the pinhole leak in the weld and any additional information that would be required for staff rev'iew. The NRC staff established through this conversation that the basis for this request was that NMP-1 has a corwnitment for NRC approval in its GL 88-01 program. It was also established that this repair was in a non-Code, non-safety related, isolable part of RWCU piping.
The licensee stated that they had not performed a detailed root cause analysis g for this through wall flaw. However, primary evaluation indicated that this weld had been sensitized to intergranular stress-corrosion cracking due to jD1 1 970 PDR P
7 175 970520 ADOCK 05000220 f
PDR l
. _ _ . . _ . _ . _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ __. _ _ _ m . _ .. _
i ..
? weld repairs made in 1997. It was further established that this repair would
- be in accordance with the NRC approved GL-88-01 program, and all applicable ;
i NRC regulatory guidance. t l'
After carefully considering the licensee action plan, and the fact that nondestructive examination cf three similar welds in the RWCU system yielded
! no indications, the NRC staff gave verbal approval (at approximately 2:30 p.m. t i EST) to the NMPC proposal and conveyed that this specific problem should not preclude NMP-1 from restart. This information was also relayed to the NRC Region I office and the NMP-1 resident inspectors. !
- FOLLOWUP '
r 1 The NRC staff requested that an updated request be submitted to the NRC staff
- i. as soon as practicable. The request should identify all commitments made to '
i the GL 88-01 program, request a formal review, and provide the technical basis j for the action plan. NMP-1 committed to send it as early next week as i possible, acknowledging that Monday, May 19th was preferable. The licensee
! agreed to conduct the evaluation of the sizing of the weld overlay.
Sincerely, l
f {dA(ht~. [e_c _
- Darl S. liood, Senior Project Manager i
Project Directorate I-I :
Division of Reactor Projects - I/II l Office of Nuclear Reactor Regulation j Docket No. 50-220 2 .
Enclosures:
- 1. Participants 1 2. Background information l'
cc w/encls: See next page
Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. I cc:
! Mr. B. Ralph Sylvia Resident Inspector 2
Executive Vice President U.S. Nuclear Regulatory Commission Generation Business Group P.O. Box 126 ,
and Chief Nuclear Officer Lycoming, NY 13093 Niagara Mohawk Power Corporation Nuclear Learning Center Charles Donaldson, Esquire 450 Lake Road Assistant Attorney General Oswego, NY 13126 New York Department of Law 120 Broadway Mr. Richard B. Abbott New York, NY 10271 Vice President and General Manager -
Nuclear Mr. Paul D. Eddy Niagara Mohawk Power Corporation State of New York Nine Mile Point Nuclear Station Department of Public Service P.O. Box 63 Power Division, System Operations Lycoming, NY 13093 3 Empire State Plaza Albany, NY 12223 Mr. Martin J. McCormick, Jr.
Vice President Mr. F. William Valentino, President Nuclear Safety Assessment New York State Energy, Research, and Support and Development Authority Niagara Mohawk Power Corporation Corporate Plaza West Nine Mile Point Nuclear Station 286 Washington Avenue Extension P.O. Box 63 Albany, NY 12203-6399 Lycoming, NY 13093 Mark J. Wetterhahn, Esquire Mr. Kn. A. Dahlberg Winston & Strawn General Manager - Projects 1400 L Street, NW Niagara Mohawk Power Corporation Washington, DC 20005-3502 Nine Mile Point Nuclear Station P.O. Box 63 Supervisor Lycoming, NY 13093 Town of Scriba Route 8, Box 382 Mr. Norman L. Rademacher Oswego, NY 13126 .
Plant Manager, Unit I ;
Nine Mile Point Nuclear Station Gary D. Wilson, Esquire P.O. Box 63 Niagara Mohawk Power Corporation Lycoming, NY 13093 300 Erie Boulevard West Syracuse, NY 13202 Ms. Denise J. Wolniak Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
l l
l t
TELECONFERENCE ATTENDEE LIST 5/16/97 Attendees HRC K. Wichman, NRR/DE/ENCB
- S. Bajwa, NRR/PDI-I W. Gleaves, NRR/PDI-1
- Hjacara Mohawk Dave Baker, Licensing Dept. 1
. Marty McCormick, VP Engineering 1 Bill Yeager, Mgr. Engineering for Unit No.1 Mcia Lee, Mechanical Design for Unit No. I Pat Bartolini, Mechanical Design Lead for Unit No.1 {
l Jim Wadsworth, ISI Program Coordinator i
Roger Carreri, Mechanical Design ;
Steve Leonard, Supr. Licensing Dept. '
Joe Thuoffe, Engineering Dept.
MPR Associates Jim Nastell Randy Trench j l
l l
l Enclosure 1 I
~
mi 697 miis:I F VP OF NSAS U2' OPS BLDG ^ ~ 5X'N5. F Il d 4T 2605 h.01
?
f Y NIAGARA i uMOHAWK
! NINE MILE PO' INT NUCLEAR STATION
- P.O. BOX 83, LYCOMING, NEW YORK 13093 i' '
, FAX COVER LETTER
! NINE MILE POINT UNIT 2 -
i- ,
j EBQM: FAX TELEPHONE NUMBER: (315) 349-1400 ff p hrGocl.
NAME: f DEPARTMENT: UCENSING/ ENVIRONMENTAL '
8 TELEPHONE NUMBER: 3 4 9 70 /e EAXl IQ: Sid h hatl>fet .3 d / 4 /5 2./ c h TOTAL NUMBER OF PAGES FAXED (INCLUDING COVER LETTER): _J_ _
DATE: TIME:
MESSAGE:y. th Or d M ! in 732.43 is (t w yitI&
t Enclosure 2
'. . . 2 . ::- . . . --- - . : .. .-
'llAY-15-97THU19:07 VP OF HSAS U2 OPS BLD0 FAX NO. 315 349 2605 P. 02 i NIAGARA MOHAWK . !
GENERATION ""5 ""8 ***'t """"'*"* ** 'm ee==am m mamm um s.am i BUSINES$ GROUP '
! aWmNJ.aseComeCK A P.E. i
- weehuseent l 4
ewwown.no May 15,1997 i
! NMPIL 1220 i ,
! l l U.S. Nuclear Regulatory thn=lsaian !
- Atta: DocumentControlDesk Washington, DC 20555
]
l RE: Nine MilePoint Unit 1 i- DudmL No. 50-220 j DDR43 i ;
hskfecer Generic Leater 30 01, "NRC k%n en KrSCC and RWR Amm=M* Sambalm
- sulrtpins" .
y .
j . (1mmtimmama
! In accendanoo with Generic istter (GL) 88-01, *NRC Position on IGSCC in BWR Austenide j Stainless stool Piping" and the NRC's Safety Evaluation Raports (SER) for Nine Mile Paint 1 Unit 1 (NhlPI) on GL V8-01, dated May 15,1990 and June 24,' 1991, this letter is to Nguest i NRC appmval of a weld oveday repair. A through-wall pin hole leakin a bimetallic (carbon i 5 piping to slainless steel nozzle) weld (33-FW.22) in the non safety related and isolable portions of the Beactor Water Cleanup SyMam (RWCU) has been discavared. Based upon our evaluation and conArmed by our consultant MPR Inc., this leak resulted from a 7/16" axial crack that has been classified as having Intergranular Stress Corrosion r=#Ma* QOSCC) in an area that was syworked during replacement of the stainless steelpiping with carbrm steel piping in 1977 (see attached Radky.$Je Examination Report NDE Report 1-5.0(MP7 0005). Our plan to repair tds weld is to pr.6.m a weld overlay which willInters ibe structunal shcogth of the wakhnent such that it will withstand design basis loads.
The design of the oveday is being performed in ancordanos with NUREG 0313 Rev. 2 and alaments af ASME Code Case N504, which is endorsed in Regulatory Guide 1.147. 'Ibese
. analyses will be available for staff asview when completed on Pdday, May 16,1997. Once installed, the weld oveday will assure structuralintegrity of this wMmant.
To assure that this weld shilure is an isolated incident, NMPC will ji.dwm mMManal ultrasonic +=minations on a sample of thres **100 welds. This sample alze is based an the planned sample expansion criteria used dv4 outages for RWCU inspections perfanned to comply with GL 38-01. If additional k.dications arm (cumd, mil erf the welds in the RWCU system which are subjnct to OL 88 C1,. augmented laWon nquiremena will be la=aa*d.
_ _ . _ _ _ _ . . - ~ _ _ . _ _ _ . _ . . . _ _ _ _ _ . _ _ _ _ _ _ _ - __ _ _ . _ .
! IIAY-15-97 THU 19:08 VP OF NSAS U2 OPS Bl.D0 1 .
FAX NO. 315 349 2605 P.03 1
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5 Pass 2 i NMP1 bds performed ultrasonic (UT) muina*Irms on six welds in the RWCU system outside ef the t'aarminmant Isolation Valva (OV)in accordance with GL 88-01, Supplement 1. Of i
the six welds, three have been UT ===minad each neueling outage ihr the last three ey--%
- cycles (RPO12,13, and 14). The sample expansion of three welds wi!! being the totalIGSCC.
j canagory 0 welds e--w outside of the CIVs to mine (two welds whleh have never basa
{ ====inad for GL 88 01 and one which was,.sbuity ereminad duririg RPO12). Therefore, ,
j 28 pescent of the welds (32) in this population win have been paminad; this includes 33-FW.~
j 22, which will be UT enminad and be rectanned to a IOSOC C@i B. It is to be noted
{ that weld 33-FW 22 was added to the GL 8801 program as part af the program review
! amooisend wishIma 96-0s.
! We curantly expoet the repair and augmented aramianHans to be completed by 2:00 p.m.,
i Friday, May 16,1997. A====Ing no further laWae are indicated based on results of the l three additional examinations, Nine Mils Point Unit 1 oculd be ready to resume operation
- (mode switch to startup) as early as midnight on May 16,1997. Itis recognimod that restart i will require NRC approval for this weld repair and alated inspections. We stand ready to j support your review with any additional infonnation that may be requimd.
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j Vice Praddant - Nuclear Fingineering
! nDM/GJG/cmk j Anuhmane l ac: Mr. H. J. Miller, Regional AdmiataW, Region I l Mr. R. R. Norris, Senior Realdent inspector l Mr. S. S. Bajwa, Acting Direcsor, Project Directorate 1-1, NRR l Mr. D. S. Hood, Senior Project Manager, NRR 1 Bacords Management y
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MAY-15-97 THU 19:00 VP OF NSAS U2 OPS BLD0 FAX NO. 315 349 2605 P.05 I
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MAY-16-97 FR1 12:21 VP OF NSAS U2 OPS BLDG FAX NO. 315 349 2005 P.03 U V'.5'D'"
FW-22 = LOCAT10N OF DEFECT FW 27 = EXPANDED SAMPLE EXAM LOCATION FW 28 = EXPANDED SAWi F FXAM 100ATION FW-55 = EXPANDED SAWLE EXAM LOCATICN s
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NOTES:
JALL N0ZZLES ARE 304 STAINLESS STEEL.
ALL PIPING IS CARBON STEEL, 6" ASTM A106 GR. B SCH. 80 EXCEPT FOR i FW-55 WHICH IS WELCCD TO 6" ASTM A376, TYPE 304 SCH. 80S STAINLESS STEEL IN0Z2LE. l THFSE WELDS ARE ALL PIPE TO N0ZZLE WELDS IN THE HIGH PRESSURE AND TEMPERATURE PIPING.
CPERAT ING PRESSURE IS APPROX. 1000 PS1G AND GPFRAT TNG TEMPERATURE IS IN THE RANGE FROM APPROX. 500 F TC 200 F. i NMPC REFERENCE DWG. C25852C SH.I
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33-FW-22 WELD OVER_AY REPA::R .
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AIDS, CP, B ."
' W' p' g ' TOE *0F WELD BETWEEN N0ZZLI Aft 0 EXIS11NG DISSiHILMt '
F t 1/4 PIPE.STANLESS STEEL S!K & WELL HETAL WELO ~ ^ ~ ~ ~
33-W-22 BiSTAG DETERMINEE Bf AMOUNI 0F s \ Y
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/ N VELD REQUIRED TO TIE IN10 EXIST [N3 W CWh WM NHtXMu p \
EXISTING WEU) d'M~EN PlW-HOLE REM HTX SHE;L AaE) N0ZZLE
- HEAT DCliANCER SHEL .
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DISTRIBUTION l
HARD COPY (with enclosures 1 & 2))
Docket File PUBLIC' PDI-l Reading OGC ACRS l
E-MAIL (with enclosure 1 only) '
\
\
-Sr-Gel 1%s/F.Miraglia- I R. Zi m.r. !
l S. Varga
-J. ZwlinskiM S. Bajwa l
D. Hood S. Little i D. Ross (e-mail to SAM) l, W. Gleaves i M. Callahan i' Gr4a4M Jr-Strosnider A l K. Wichman l K.' Cotton W. Dean L. Doerflein, RI t
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weld repairs made in 1997. It was further established that this repair would be in accordance with the NRC approved GL-88-01 program, and all applicable NRC regulatory guidance.
After carefully considering the licensee action plan, and the fact that nondestructive examination of three similar welds in the RWCU system yielded no indications, the NRC staff gave verbal approval (at approximately 2:30 p.m.
EST) to the NMPC proposal and conveyed that this specific problem should not preclude NMP-1 from restart. This information was also relayed to the NRC Region I office and the NMP-1 resident inspectors.
~
4 FOLLOWUP The NRC staff requested that an updated request be submitted to the NRC staff as soon as practicable. The request should identify all commitments made to the GL 88-01 program, request a formal review, and provide the technical basis for the action plan. NMP-1 committed to send it as early next week as possible, acknowledging that Monday, May 19th was preferable. The licensee agreed to conduct the evaluation of the sizing of the weld overlay.
Sincerely, h $W kC
/
Darl S. H,.od, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosures:
- 1. Participants
- 2. Background information cc w/encls: See next page DOCUMENT NAME:NMP72442.TEL To r:ceive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment /englosure "N" - No copy 0FFICE PM:PDI-1 lE PM:PDI 1 lE LA:PDI-1 M l D:PDI-1 ,,p % l I l
,NAME WGleaves:mw W (o DMood w(4 t -, e SLittle F SBajwa //
- P DATE 05/./o /97 05/ n /97 05/ @ /97 05/qB97 05/ /97 Official Record Copy
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