Letter Sequence Meeting |
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MONTHYEARML20202J2031999-01-28028 January 1999
Summary of 990107 Meeting with NSP Re Recent License Amend Request for PINGP Ts.List of Meeting Participants & NSP Meeting Presentation Slides Encl
Project stage: Meeting
1999-01-28
[Table View] |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20206G5151999-04-30030 April 1999
Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl
ML20207L7711999-03-11011 March 1999
Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP
ML20202J2031999-01-28028 January 1999
Summary of 990107 Meeting with NSP Re Recent License Amend Request for PINGP Ts.List of Meeting Participants & NSP Meeting Presentation Slides Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20249C4711998-06-24024 June 1998
Summary of 980611 Meeting W/Wog in Rockville,Md Re Part Length CRDM Issues.List of Attendees & Matl Presented at Meeting Encl
ML20217E1231997-09-25025 September 1997
Summary of 970826 Meeting W/Nsp Re Plant Revised MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration in Boric Acid Storage Tanks.List of Attendees & Handouts Encl
ML20140H9181997-05-0909 May 1997
Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl
ML20137W3311997-04-17017 April 1997
Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20128H9581993-02-10010 February 1993
Summary of 930202 Meeting W/Util Re Proposed Amend Requests Currently Under Review.Amends Included,Refueling & Fuel Handling Spec Changes,Containment Penetration List Removal & Instrumentation Spec Changes
ML20151Q8131988-08-0303 August 1988
Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl
ML20154A8991988-05-0404 May 1988
Summary of Operating Reactors Events 88-18 Meeting on 880503 Re Events Which Occurred Since 880426 Meeting.List of Attendees & Viewgraphs Encl
ML20237G3891987-08-27027 August 1987
Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20236K6701987-07-13013 July 1987
Summary of 870713 Public Hearing on Northern States Power Co Fuel Rod Consolidation Pilot Project in St Paul,Mn
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137Y6641985-11-25025 November 1985
Summary of 851106 Meeting W/Util & B&W Re Reliability of Auxiliary Feedwater Sys.List of Attendees Encl
ML20237B0671985-11-25025 November 1985
Summary of 851106 Meeting W/Util Re Reliability of Auxiliary Feedwater Sys.List of Attendees & Licensee Viewgraphs Encl
ML20209G2111985-08-23023 August 1985
Trip Rept of 850715 Site Visit to Participate in INPO Training Accreditation Site Team Activities.Weaknesses Included Lack of Accreditation for Mgt Training & Evaluation Criterion
ML20133F7531985-07-31031 July 1985
Summary of 850626 Meeting W/Util & Westinghouse Re Upcoming Changes to Reactor Internals & Impact on Tech Specs.Licensee Plans to Change from Exxon Fuel to Westinghouse Fuel.Agenda & Attendance List Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062H3561979-12-12012 December 1979
Summary of 791126 Meeting W/Westinghouse & Util Re Base Metal Cracking in Reactor Vessel Nozzles Under Stainless Steel Cladding
ML20062F5591978-12-12012 December 1978
Summary of 781026 Meeting to Discuss Tech Specs for Secondary Water Chem,Reactor Coolant Activity & Secondary Coolant Activity
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20127H6361977-11-0101 November 1977
Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20128F4251977-03-10010 March 1977
Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
ML20126C1851976-03-24024 March 1976
Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl
1999-04-30
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20206G5151999-04-30030 April 1999
Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl
ML20207L7711999-03-11011 March 1999
Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP
ML20202J2031999-01-28028 January 1999
Summary of 990107 Meeting with NSP Re Recent License Amend Request for PINGP Ts.List of Meeting Participants & NSP Meeting Presentation Slides Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20249C4711998-06-24024 June 1998
Summary of 980611 Meeting W/Wog in Rockville,Md Re Part Length CRDM Issues.List of Attendees & Matl Presented at Meeting Encl
ML20217E1231997-09-25025 September 1997
Summary of 970826 Meeting W/Nsp Re Plant Revised MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration in Boric Acid Storage Tanks.List of Attendees & Handouts Encl
ML20137W3311997-04-17017 April 1997
Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20128H9581993-02-10010 February 1993
Summary of 930202 Meeting W/Util Re Proposed Amend Requests Currently Under Review.Amends Included,Refueling & Fuel Handling Spec Changes,Containment Penetration List Removal & Instrumentation Spec Changes
ML20151Q8131988-08-0303 August 1988
Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl
ML20154A8991988-05-0404 May 1988
Summary of Operating Reactors Events 88-18 Meeting on 880503 Re Events Which Occurred Since 880426 Meeting.List of Attendees & Viewgraphs Encl
ML20237G3891987-08-27027 August 1987
Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137Y6641985-11-25025 November 1985
Summary of 851106 Meeting W/Util & B&W Re Reliability of Auxiliary Feedwater Sys.List of Attendees Encl
ML20237B0671985-11-25025 November 1985
Summary of 851106 Meeting W/Util Re Reliability of Auxiliary Feedwater Sys.List of Attendees & Licensee Viewgraphs Encl
ML20133F7531985-07-31031 July 1985
Summary of 850626 Meeting W/Util & Westinghouse Re Upcoming Changes to Reactor Internals & Impact on Tech Specs.Licensee Plans to Change from Exxon Fuel to Westinghouse Fuel.Agenda & Attendance List Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062H3561979-12-12012 December 1979
Summary of 791126 Meeting W/Westinghouse & Util Re Base Metal Cracking in Reactor Vessel Nozzles Under Stainless Steel Cladding
ML20062F5591978-12-12012 December 1978
Summary of 781026 Meeting to Discuss Tech Specs for Secondary Water Chem,Reactor Coolant Activity & Secondary Coolant Activity
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20127H6361977-11-0101 November 1977
Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20128F4251977-03-10010 March 1977
Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
ML20126C1851976-03-24024 March 1976
Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl
1999-04-30
[Table view] |
Text
_ _ _ _ _ _ _ _ . _ __ ._ __ _ _
n u I '
- g fp ce:%,*a UNITED STATES 7
, g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001 f\Lb o
Y.....[ January 28, 1999 .,f M f f y/hp6 LICENSEE: Northern States Power Company l FACILITY: ' Prairie Island Nuclear Generating Plant 1
SUBJECT:
MEETING BETWEEN THE NORTHERN STATES POWER COMPANY AND THE NRC STAFF CONCERNING A LICENSE AMENDMENT REQUEST FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT (TAC NOS: MA4228/MA4229)
The NRC staff met with representatives from the Northern States Power Compariy (NSP) at NRC Headquarters on January 7,1999, concerning a recent license amendment request dated November 25,1998, for the Prairie Island Nuclear Generating Plant (PINGP). Enclosure 1 lists the meeting participants. A public meeting notice for the subject meeting was issued on December 21,1998, and a copy of the meeting notice had been posted on the NRC's public Internet webpage.
The NSP's license amendment request proposed changes to the PINGP technical specifications (TS) that would append specific allowed-outage time provisions pertaining to the boric acid storage tank (BAST) level channels and transfer logic channels for required testing and maintenance. NSP requested the meeting to brief the staff on the background of the subject amendment request and also to step through the relevant logic system diagrams with the staff. Enclosure 2 is a copy of the licensee's slides (simplified logic system / functional diagrams) used during the meeting. The consensus among the staff members who attended the meeting was that the meeting was very helpfulin understanding the relatively complicated logic systems involved in the subject amendment request as well as the licensee's need for the amendment, and therefore preempting the need for a staff request for additionalinformation.
As a result, the staff expects to be able to accommodate the licensee's request for an expedited review schedule.
PINGP TS requires the operability of BAST interlocks associated with the transfer of safety ,
injection suction from BAST to the refueling water storage tank (RWST). The TS also require the functional testing of the BAST transfer logic to the RWST on a monthly basis. However, the TS do not provide specific allowed-outage-time to perform the required testing. As reported in its Licensee Event Report 98-18, dated December 17,1998, since orig!nal plant operation, NSP has performed the analog testing of BAST level channels by placing the respective channels in the tripped condition. When in this condition, a single failure of another channel could have caused a premature transfer of the safety injection pump suctions from the BAST to RWST g I
which would bypass the injection of highly borated water required to mitigate a main steam line \ ;
break accident. This discrepancy was identified by NSP as a resuit of a followup to NRC Information Notice 97-81," Deficiencies in Failure Modes and Effects Analyses for Instrumentation and Control Systems."
p 9902090062 990128 PDR ADOCK 05000282 P PDR fff f
.-.. -. ,. .~ - .- ._ . .- . . . - . . .. .- .
2 Subsequent to identification of this discrepancy. NSP determined that it is possible to perform the required testing without making level or logic channels associated with the inservice BASTS isolated. However, testing the instrumentation in that manner requires the physical realignment of the standby and inservice BASTS on each unit each month. This testing configuration has several disadvantages and increases the potential for a two-unit shutdown resulting from the inability to complete the required testing when and if one of the three BASTS are found to be inoperable. Therefore, it is not considered a viable method for the long-term testing of the BAST instrumentation. Hence, the proposed TS amendment appends specific allowed-outage-time provisions for the BAST level channels and transfer log *c channels for required testing and maintenance.
ORIGINAL SIGNED BY Tae Kim, Senior Project Manager ;
Project Directorate ill-1 Division of Reactor Projects - Ill/IV
- Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
As stated cc w/encts: See next page DISTRIBUTION:
HARD COPY Docket File (50-282,50-306) PUBLIC PD#3-1 Reading T. J. Kim ,
OGC ACRS l l
E-MAIL i S. Collins /R. Zimmerman B. Sheron B. Boger E. Adensam C. A. Carpenter C. Jamerson ,
B. Marcus M. Weston !
J. Wermiel W. Beckner T. Hiltz B. Burgess S. Ray DOCUMENT NAME: G:\PD3-1\WPDOCS\ PRAIRIE \MTG4228.WPD To recehre a eq y of this document, ineNcato in the box: "C" = Copy without attachment /encbsure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PD31 ' E LA:PD31 l( PD:PD3-1 l C, NAME TJKim1/4 CJamerson' CACarpente(9i i DATE 1/ y//s9 1/ t1/997 1 / 1 6 /99 i
l/ OFFICIAL RECORD COPY
)
.~. .. . . . - - . . . . .- ----. - - . . - . -
['
t Northem States Power Company Prairie Island Nuclear Generating Plant cc:
Site Licensing I J. E. Silberg, Esquire Prairie Island Nuc sear Generating ;
Shaw, Pittman, Potts and Trowbridge Plant .
2300 N Street, N. W. Northem States Power Company !
Washington DC 20037 1717 Wakonade Drive East ;
Welch, Minnesota 55089 l Plant Manager Prairie Island Nuclear Generating Tribal Council :
Plant . Prairie Island Indian Community ;
Northern States Power Company ATTN: EnvironmentalDepartment 1717 Wakonade Drive East 5636 Sturgeon Lake Road Welch, Minnesota 55089 Welch, Minnesota 55089 Adonis A. Noblett Mr. Roger O. Anderson, Director Assistant Attorney General Nuclear Energy Engineering Office of the Attorney General Northem States Power Company 455 Minnesota Street 414 Nicollet Mall Suite 900 Minneapolis, MN 55401 St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Commission
' Resident inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region lli U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532 4351 Mr. Stephen Bloom, Administrator Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Ocpartment of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 June 1998
, _ , * '~: --- ^~__ , , . _ . _
l .
4 LIST OF MEETING ATTENDEES NAME AFFILIATION I
T. J. Kim NRC/NRR/DRPW/PD31, Project Manager - Prairie Island .
B. Marcus NRC/NRR/DRCH/HICB, Technical Reviewer M. Weston NRC/NRR/ADP/TSB, Technical Reviewer E. Eckholt Northern States Power C. Mundt Northem States Power i
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t V v t To Train A To Train A To Train B To Train B Logic Logic Logic Logic Unit 2 Unit 2 (121 BAST (121 BAST Only) Only)
.--__________-_- - _ ____-_ _ ________________ _______ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
