Letter Sequence Meeting |
---|
|
|
MONTHYEARML20245C3211977-07-11011 July 1977 Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls Project stage: Meeting ML20071F4931978-10-0404 October 1978 Forwards Proposed Tech Specs for Overpressure Protec Per NRC 780828 Request.No Fee Encl Should Be Considered as Part of the Original Submittal Which Predates Fee Schedule Requirements of 10CFR170.22a Project stage: Other ML20065A9221983-02-0808 February 1983 Forwards Responses to NRC Re Open Items in Sections 3.4, Single Failure Criteria & 3.5, Seismic Design, of Technical Evaluation Rept EGG-EA-5826, Reactor Vessel Overpressure Protection Project stage: Other 1978-10-04
[Table View] |
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O EnclsML20245C321 |
Person / Time |
---|
Site: |
Beaver Valley, Salem, Kewaunee, Point Beach, Prairie Island, Surry, Turkey Point, Ginna, Robinson, San Onofre, Cook, Zion, 05000000, Trojan |
---|
Issue date: |
07/11/1977 |
---|
From: |
Zech G Office of Nuclear Reactor Regulation |
---|
To: |
Office of Nuclear Reactor Regulation |
---|
References |
---|
TAC-6714, NUDOCS 8710260123 |
Download: ML20245C321 (4) |
|
Similar Documents at Beaver Valley, Salem, Kewaunee, Point Beach, Prairie Island, Surry, Turkey Point, Ginna, Robinson, San Onofre, Cook, Zion, 05000000, Trojan |
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217M5371999-10-25025 October 1999 Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl ML20211N2141999-09-0808 September 1999 Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl ML20210Q7891999-08-10010 August 1999 Summary of 990713 Conference Call with Util Re Licensee Proposed Exemption Request ,as Supplemented by Ltr Re Emergency Preparedness ML20195J8561999-06-16016 June 1999 Summary of 990518 Meeting with Dlc & Westinghouse to Discuss Dlc License Amend Request to Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20207H3531999-06-14014 June 1999 Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl ML20206Q6411999-05-12012 May 1999 Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl ML20206P0831999-05-12012 May 1999 Summary of 990428 Meeting with Firstenergy Nuclear Operating Co & Duquesne Light Co in Rockville,Maryland Re Proposed Asset Transfer Between Firstenergy Corp & Dl & Resulting 10CFR50.80 License Transfer of Dl Ownership Interest ML20206G5151999-04-30030 April 1999 Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl ML20206K2201999-04-19019 April 1999 Summary of 990311 Meeting with Util Re Action Plan for Correcting Design Deficiencies of Various Small Bore Piping Supports 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 ML20203A9151999-02-0404 February 1999 Summary of 990119 Meeting with Util Re Current & Anticipated Licensing Issues for Plant,Units 1 & 2.List of Meeting Attendees & Handout Matl Encl 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 ML20199E1051999-01-13013 January 1999 Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl ML20198B7641998-12-16016 December 1998 Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List 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 ML20155C5561998-10-28028 October 1998 Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl 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 NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998 Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl ML20216B8551998-05-0707 May 1998 Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees ML20217N9551998-03-23023 March 1998 Summary of 980317 Meeting W/Ceco at Opus Ofc of Ceco Re Update on Current Station Decommissioning Status & Plans. Generic Timeline,Collection of Decommissioning Plans & Description of Backlog Evaluation Process Encl ML20203G0581998-02-23023 February 1998 Summary of 980113 Meeting W/Util Re Plans & Preparations to Implement Zion Improved Ts.List of Attendees & Meeting Handouts Encl ML20203H5141998-02-23023 February 1998 Summary of 980203 Meeting W/Util Re Plans to Decommmission Plant,Units 1 & 2.List of Attendees & Licensee Visual Aids Encl ML20203A3531998-01-29029 January 1998 Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl ML20198A3731997-12-0404 December 1997 Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP ML20199G7121997-11-0606 November 1997 Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides 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 ML20210T1921997-08-26026 August 1997 Summary of 970805 Meeting W/Duquesne Light Co in Rockville, MD to Discuss Info Re Pressurized Thermal Shock Evaluation ML20210H3881997-08-0808 August 1997 Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl ML20141H7051997-05-19019 May 1997 Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees 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 ML20147E8501997-03-17017 March 1997 Summary of Operating Reactors Events Meeting 97-02 on 970312.List of Attendees,Significant Elements of Discussed Events & Reactor Scram Statistics for Weeks Ending Feb 16, 23,Mar 2 & 9 Encl ML20135F7891997-03-0303 March 1997 Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles ML20137D5231997-01-23023 January 1997 Summary of 970103 Meeting W/Util in Lisle,Il Re Findings from Util Contracted ISA & Effects of Recently Identified Technical Issue Involving Degraded Containment Paint Coatings on Readiness for Restart of Unit 2 ML20134A9621997-01-22022 January 1997 Summary of 961204 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Centerior Energy Corporation & Ohio Edison Company.List of Attendees & Info Handouts Encl ML20138H6081997-01-0202 January 1997 Summary of 961115 Meeting W/Util Re Results of Steam Generator Tube Insp & Repairs of Plant ML20136A8611996-11-27027 November 1996 Partially Withheld Summary Meeting W/Florida Power & Light Held on 961121 Re General Update on FPL Nuclear Plants ML20128L1911996-10-0909 October 1996 Summary of 960828 Meeting W/Ceco to Discuss Plant Improved Std Ts.List of Attendees & Licensee Handout Encl ML20129E2231996-09-24024 September 1996 Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20217D4661995-12-0404 December 1995 Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources ML17309A5401994-04-13013 April 1994 Summary of 940324 Public Meeting W/Util to Discuss Steam Generator Replacement & Fuel Reload Changes for 1996.Agenda Encl ML20059F2621994-01-10010 January 1994 Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility ML20059H7581994-01-0303 January 1994 Summary of Operating Reactors Events Meeting 93-48 on 931222 ML20058N4851993-12-15015 December 1993 Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML20058K1301993-11-29029 November 1993 Summary of Operating Reactors Events Meeting 93-44 on 931124 ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20058B5681993-11-18018 November 1993 Trip Rept of 931102 Meeting Between NRC & Util Re Planned Research on naturally-aged Cables from Plant 1999-09-08
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217M5371999-10-25025 October 1999 Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl ML20211N2141999-09-0808 September 1999 Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl ML20210Q7891999-08-10010 August 1999 Summary of 990713 Conference Call with Util Re Licensee Proposed Exemption Request ,as Supplemented by Ltr Re Emergency Preparedness ML20195J8561999-06-16016 June 1999 Summary of 990518 Meeting with Dlc & Westinghouse to Discuss Dlc License Amend Request to Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20207H3531999-06-14014 June 1999 Summary of 990317 Meeting with SCE Re Issues Staff Identified in Review of 980910 License Amend Application & Exemption Request to Remove Hydrogen Monitoring & Control Sys from SONGS Licensing Basis.Meeting Attendee List Encl ML20206Q6411999-05-12012 May 1999 Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl ML20206P0831999-05-12012 May 1999 Summary of 990428 Meeting with Firstenergy Nuclear Operating Co & Duquesne Light Co in Rockville,Maryland Re Proposed Asset Transfer Between Firstenergy Corp & Dl & Resulting 10CFR50.80 License Transfer of Dl Ownership Interest ML20206G5151999-04-30030 April 1999 Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl ML20206K2201999-04-19019 April 1999 Summary of 990311 Meeting with Util Re Action Plan for Correcting Design Deficiencies of Various Small Bore Piping Supports 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 ML20203A9151999-02-0404 February 1999 Summary of 990119 Meeting with Util Re Current & Anticipated Licensing Issues for Plant,Units 1 & 2.List of Meeting Attendees & Handout Matl Encl 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 ML20199E1051999-01-13013 January 1999 Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl ML20198B7641998-12-16016 December 1998 Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List 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 ML20155C5561998-10-28028 October 1998 Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl 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 NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998 Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl ML20216B8551998-05-0707 May 1998 Summary of 980429 Meeting W/Southern California Edison in Rockville,Maryland Re Proposed Amend to TS to Allow Operation of Plant at Reduced Tcold in Reactor Coolant Sys. W/Meeting Slides & List of Meeting Attendees ML20217N9551998-03-23023 March 1998 Summary of 980317 Meeting W/Ceco at Opus Ofc of Ceco Re Update on Current Station Decommissioning Status & Plans. Generic Timeline,Collection of Decommissioning Plans & Description of Backlog Evaluation Process Encl ML20203G0581998-02-23023 February 1998 Summary of 980113 Meeting W/Util Re Plans & Preparations to Implement Zion Improved Ts.List of Attendees & Meeting Handouts Encl ML20203H5141998-02-23023 February 1998 Summary of 980203 Meeting W/Util Re Plans to Decommmission Plant,Units 1 & 2.List of Attendees & Licensee Visual Aids Encl ML20203A3531998-01-29029 January 1998 Summary of 971223 Meeting W/Sce in Rockville,Md to Discuss Mechanical Nozzle Seal Assembly Relief Request.List of Attendees & Slides Encl ML20198A3731997-12-0404 December 1997 Summary of 971119 Meeting W/Westinghouse Owners Group Re Completion of WOG Topical Rept WCAP-14572,rev 1,conclusions from Results of Surry Pilot Plant Submittal & Schedule for Approving Surry Submittal & Associated WCAP ML20199G7121997-11-0606 November 1997 Summary of 971023 Meeting W/Util in Rockville,Md Re Results of Steam Generator Tube Degradation & Run Time Analysis for SONGS Unit 2.List of Attendees & Slides 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 ML20210T1921997-08-26026 August 1997 Summary of 970805 Meeting W/Duquesne Light Co in Rockville, MD to Discuss Info Re Pressurized Thermal Shock Evaluation ML20210H3881997-08-0808 August 1997 Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl ML20141H7051997-05-19019 May 1997 Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees 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 ML20147E8501997-03-17017 March 1997 Summary of Operating Reactors Events Meeting 97-02 on 970312.List of Attendees,Significant Elements of Discussed Events & Reactor Scram Statistics for Weeks Ending Feb 16, 23,Mar 2 & 9 Encl ML20135F7891997-03-0303 March 1997 Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles ML20137D5231997-01-23023 January 1997 Summary of 970103 Meeting W/Util in Lisle,Il Re Findings from Util Contracted ISA & Effects of Recently Identified Technical Issue Involving Degraded Containment Paint Coatings on Readiness for Restart of Unit 2 ML20134A9621997-01-22022 January 1997 Summary of 961204 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Centerior Energy Corporation & Ohio Edison Company.List of Attendees & Info Handouts Encl ML20138H6081997-01-0202 January 1997 Summary of 961115 Meeting W/Util Re Results of Steam Generator Tube Insp & Repairs of Plant ML20136A8611996-11-27027 November 1996 Partially Withheld Summary Meeting W/Florida Power & Light Held on 961121 Re General Update on FPL Nuclear Plants ML20128L1911996-10-0909 October 1996 Summary of 960828 Meeting W/Ceco to Discuss Plant Improved Std Ts.List of Attendees & Licensee Handout Encl ML20129E2231996-09-24024 September 1996 Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20217D4661995-12-0404 December 1995 Summary of 950911 Meeting W/Commonwealth Edison Re Util Commitment to Improving Dresden,Matl Condition at Zion, Declining Performance at Braidwood & Comed Resources ML17309A5401994-04-13013 April 1994 Summary of 940324 Public Meeting W/Util to Discuss Steam Generator Replacement & Fuel Reload Changes for 1996.Agenda Encl ML20059F2621994-01-10010 January 1994 Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility ML20059H7581994-01-0303 January 1994 Summary of Operating Reactors Events Meeting 93-48 on 931222 ML20058N4851993-12-15015 December 1993 Summary of 931119 Meeting W/Sce in Rockville,Md Re Proposed Decommissioning Plan for SONGS 1.List of Attendees Encl ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML20058K1301993-11-29029 November 1993 Summary of Operating Reactors Events Meeting 93-44 on 931124 ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20058B0031993-11-10010 November 1993 Summary of 931103 Meeting W/Util in Rockville Re Emergency Diesel Generator Addition Project.Attendance List,Discussion on Proposed Review Schedule & Licensee Summary of Emergency Diesel Generator Project Encl ML20059L2351993-11-0808 November 1993 Summary of 930930 Meeting W/Util at Zion Nuclear Power Station Re Electronic Fire Watch Sentry Program Being Considered for Use at Zion Nuclear Power Station.List of Attendees Encl 1999-09-08
[Table view] |
Text
GW~
ij g*
p' 4 UNITED STATES NUCLEAR REGULATORY COMMISSION uc p
c7i WASHINGTON, D. C. 20565 -
) .g j July 11, 1977
)}k 1 -
j DOCKET NOS: E0-334, 50-315, 50-244, 50-305, 50-266, 50-301, 50-282, 50-306, 50-261, iS0-206d 50-280, 50-281, 50-344, 50-250, l 50-251, 50-295, 50-304 and 50-272 LICENSEE / FACILITY: Duquesne Light Company (Beaver Vally Unit 1),
Indiana & Michigan Power Co. (D.C. Cook Unit 1)
Rochester Gas & Electric Corp. (R. E. Ginna)
Wisconsin Public Service Corp. (Kewaunee)
Wisconsin Electric Power Co. (P. Beach 1 &2)
Northern States Power Co. (Prairie Island Units 1 &2)
Carolina Power & Light Co. (H.B. Robinson Unit 2) !
Northeast Utilities ( Haddam Neck)
Southern California Edison Co. (San Onofre)
Virginia Electric & Power Co. (Surry Units 1&2)
Florida Power & Light Co. (Turkey Point Units 3&4)
Portland General Electric Co. (Trojan)
Commonwealth Edison Co. Zion Units 1&2)
Consolidated Edison Co. Indian Point Unit.2&3)
SUMMARY
OF MEETING HELD ON MAY 25, 1977, WITH WESTINGHOUSE AND THE LICENSEES OF WESTINGHOUSE - DESIGNED PWR FACILITIES CONCERNING THE STATUS OF THEIR EFFORTS TO PREVENT REACTOR VESSEL OVERPRESSURIZATION On May 25, 1977, we met with representatives of Westinghouse Electric i Corporation and members of the Westinghouse Utility Group on Reactor Vessel Overpressurization, representing the licensee of each Westinghouse designed operating PHR facility (except Yankee Rowe and Salem), to discuss the results of a generic analysis conducted to determine the severity of potential pressure transients at these facilities and to review proposed measures to prevent or mitigate such transients.
A list of attendees is attached.
Significant discussions and agreements are summarized below.
The Utility Group chairman summarized the earlier activities by its members in determining a solution to the problem of reactor vessel ,
I overpressurization and indicated that their consultant, Westinghouse, had completed the generic transient analysis for the Westinghouse PWR plants. l This analysis is intended to be a boundary-type of analysis, using input l
}
parameters such that all members of the Utility Group will be able to i reference the analysis in their forthcoming plant-specific submittals.
The conclusion reached by the licensee as a result of the analysis is that a single power-operated pressurizer relief valve will mitigate pressure transients. (However, some overshoot of Appendix G limits results in certain transient conditions) 8710260123 770711 J PDR ADOCK 05000206 i
\
P PDR L____________________________ __ l
~ ..
i 1
Meeting Sumnary Numerous Utilities )
i Westinghouse representatives then provided a presentation of the detailed I results of the transient analysis. Copies of the presentation and the l transient analysis results are attached.
The Westinghouse analysis- considered both the mass imput and the heat ,
input types of transients. As indicated above, the method of overpressure i protection assumed in the analysis is a pressurizer power operated relief valve. The effect of two power-operated relief valves on setpoint overshoot 1 was included, although credit is taken for only one valve due to single failure !
cri teria. A discussion was provided of the various reference parameters used for each of the two basic types of transients analyzed. The results of the analysis show that the start of a Safety Injection (SI) pump while in a !
water-solid condition is the worst-cause transient of the mass input types l reviewed. The staff was advised that for such a transient, some overshoot 1 of Appendix G limits is predicted to result. The peak pressure noted in the analysis was about 800 psig.
The results of the heat input type of transient show that the worst ]
case transient is caused by a reactor coolant pump start, while water {
solid, with a temperature differential between the reactor coolant -
system (RCS) and a steam generator. With a AT of up to 50'F the single PORV would mitigate the transient with a setpoint overshoot of about 100 psi (PORV setpoint of 600 psig), with an initial RCS temperature of 180 F.
The effects observed by varying the various input parameters were shown and a summary was than made of the two types of transients reviewed. With I regard to the conservatism in the analysis, we advised the licensees that if properly substantiated, credit could be taken for the conservatism )
identified. {
I The staff advised the licensees that, as indicated at our November 4,1976 !
l meeting and in separate correspondence with each of the licensees, the I Appendix G limits for each of the facilities should not be exceeded as a result of a reactor coolant system pressure transient. Since the Westing-house generic analysis is a bounding-type of analysis, each licensee should show in its plant-specific submittal that the parameters applicable to their plant will not result in Appendix G limits being exceeded. For those facilities ,
which cannot demonstrate that the Appendix G limits will be met, further !
analyses and review may be necessary.
i l
l l
I
_ _ _ _ - - - - 1
,o<
- )
l Meeting Summary -
3-Numerous Utilities >
1 The Westinghouse generic analysis is to be submitted about mid-June 1977 and following a review by each licensee to determine the applicability .
of the results of the analysis to their facility, a plant-specific analysis l will be provided to the staff in late June 1977. ;
l In summary, the staff indicated that the following should be considered be each licensee and/ included in its submittal: a 1.. Previous submittals defered addressing acceptance criteria until ,
the generic analysis was completed. This information should now {
be provided. 1 I
- 2. The plant conditions, components and systems that are to be l controlled by administrative procedures should be identified and ]
appropriate Tech Spec changes proposed. This should include the !
l components or systems assumed to be unavailable and therefore not considered in the transient analyses.
- 3. Include electrical schematics and logic diagrams for protective ]
system control circuitry. l I
i
- 4. A dual setpoint enabling alarm must be included; a computer-generated alarm is not acceptable. The alarm must be "hard-wired" to the PORV isolation valve to assure that it is opened when j required. In response to a question asked during the meeting, the a valve position indicator lights are not acceptable for this purpose.
- 5. Additional details should be provided on the modeling of PORV's.
The effects of flashing on assumed relief capacity should be con-sidered.
l
- 6. An explanation of how the criteria will be satisfied should be i I
provided regarding the loss of air / loss of offsite power.
1 i
l l
l j
- - - - - - ~ - - - - -
-f
.y
, i l
Meeting Summary Numerous Utilities I 1
- 7. The final design must be capable of satisfying Appendix G limits
i over the 40 year life of the plant. If the 40 year period can-not be met initially, a licensee may elect to propose meeting a' (
lesser Appendix G fluence level, but with the understanding that the design would be considered to be interim.in.na_ture and a final design must be proposedland implemented within the.next' l'i )
refueling outage.
f 4
Gary Zech, Project Manager Operating Reactors Branch #1 Division of Operating Reactors
Enclosure:
- 1. List of Attendees .
j
- 2. Utility Group on Overpressurization - Meeting Agenda
- 3. Transient analysis results ,
c i
_ . _ _ . _