Similar Documents at Perry |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217H1001999-10-13013 October 1999 Summary of 990930 Meeting with Util in Rockville,Md Re Proposed Five Percent Power Uprate for Plant,Unit 1.List of Meeting Participants & Licensee Meeting Handout Encl ML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities 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 ML20206D6031999-04-30030 April 1999 Summary of 990318 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Review Schedule & Content of Proposed QA Topical Rept for Both Davis-Besse & Perry Facilities.List of Meeting Attendees Encl ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl ML20198S3061999-01-0505 January 1999 Summary of 981204 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys ML20198D5801998-12-15015 December 1998 Summary of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys ML20202D3521998-12-0909 December 1998 Summary of 981123 Petition Review Board Meeting Re 2.206 Petition on Perry Unit 1,submitted on 981109 by Ucs.Meeting Attendees Listed ML20155H3801998-10-29029 October 1998 Summary of 980915 Meeting with Util & Contractor Polestar Applied Technology,Inc in Rockville,Md Re Revised Accident Source Term for Perry Pilot Plant Review.List of Meeting Participants & Nonproprietary Handouts Encl ML20154J3671998-10-13013 October 1998 Summary of 980910 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md Re Licensee Proposed Changes to Design & Licensing Basis to Containment Isolation Provisions for Feedwater System.List of Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20199L2071997-11-24024 November 1997 Trip Rept of 971006 Visit to Perry Site to Gather Info on New & Unique Strainer Design Installed at Perry During Most Recent Outage ML20141E7701997-05-14014 May 1997 Summary of 970508 Meeting W/Cei in Rockville,Md Re Priorities & Schedules of Licensing Issues for Plant,Unit 1. List of Meeting Attendees & Meeting Handout Encl ML20140H4881997-05-0707 May 1997 Provides Summary of 970401 Telcon Between NRC & BWROG Re Topical Rept NEDC-31858P,Rev 2, BWROG Rept for Increasing MSIV Leakage Rate Limits & Elimination of Leakage Control Sys ML20138D9441997-04-23023 April 1997 Summary of 970324 Meeting W/Licensee in Rockville,Md Re ECCS suction-strainer Program for Perry Npp,Unit 1.List of Attendees & Viewgraphs Encl 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 ML20147A7261997-01-22022 January 1997 Summary of 960910 Meeting W/Util in Rockville,Md to Discuss Revised Eal.List of Attendees Encl ML20062J8701993-11-0808 November 1993 Summary of 931028 Meeting W/Licensee in Rockville,Md Re Licensee Presentation of Summary of Plant Course of Action Plan to NRC Mgt ML20057F1271993-10-0505 October 1993 Summary of 930902 Meeting W/Util in Rockville,Md Re NRC 930405 Safety Evaluation of Rev 3 to IST Program.List of Attendees 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 ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20206D7761988-11-0808 November 1988 Summary of 881102 Meeting W/Util in Rockville,Md Re Facility Operating Performance.External Performance Assessments, Performance Indicators,Mgt Initiatives & Feedback Effectivness Discussed.Agenda & Viewgraphs Encl ML20207N9071988-10-12012 October 1988 Summary of 881006 Meeting W/Licensee & GE Re Forthcoming Reload Submittal for Feb 1989 Reload.Attendees List & Nonproprietary Slides Presented by GE Outlining Scope of Reload Application to Be Submitted by Nov 1988 Encl ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20150D7171988-07-0707 July 1988 Summary of Operating Reactors Events Meeting 88-26 on 880628 ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams Encl ML20153G5481988-05-0404 May 1988 Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items 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 ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20239A0231987-09-10010 September 1987 Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl ML20207A5221987-05-15015 May 1987 Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20204E5421987-03-19019 March 1987 Summary of Operating Reactors Events Meeting 87-06 on 870309.List of Attendees & Events Discussed & Significant Elements of Events Presented Encl ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20215D0631986-12-11011 December 1986 Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed 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 ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20215D9171986-10-0606 October 1986 Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl ML20210C4211986-09-11011 September 1986 Summary of Operating Reactors Events Meeting 86-31 on 860908.Lists of Attendees,Events & Significant Elements & Assignments Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20199L5241986-06-30030 June 1986 Summary of 860611 Meeting W/Util,Usgs,Weston Geophysical, Shaw-Pittman Assoc,Geosciences Svcs,Univ of South Carolina, Gilbert Commonwealth Assoc & Nts Engineering Re Completion of Earthquake Confirmatory Items in Sser 9 ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20198D5391986-05-12012 May 1986 Summary of 860430 Meeting W/Util,Nts Engineering,Usgs, Gilbert Commonwealth,Weston Geophysical,Geoscience Svcs & Univ of South Carolina Re Earthquake Confirmatory Work Required in Sser 9.Attendance List Encl 1999-08-04
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217H1001999-10-13013 October 1999 Summary of 990930 Meeting with Util in Rockville,Md Re Proposed Five Percent Power Uprate for Plant,Unit 1.List of Meeting Participants & Licensee Meeting Handout Encl ML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities 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 ML20206D6031999-04-30030 April 1999 Summary of 990318 Meeting with Firstenergy Nuclear Operating Co in Rockville,Maryland Re Review Schedule & Content of Proposed QA Topical Rept for Both Davis-Besse & Perry Facilities.List of Meeting Attendees Encl ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing Encl ML20198S3061999-01-0505 January 1999 Summary of 981204 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys ML20198D5801998-12-15015 December 1998 Summary of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Changes to Design & Licensing Basis of Containment Isolation Provisions for Feedwater Sys ML20202D3521998-12-0909 December 1998 Summary of 981123 Petition Review Board Meeting Re 2.206 Petition on Perry Unit 1,submitted on 981109 by Ucs.Meeting Attendees Listed ML20155H3801998-10-29029 October 1998 Summary of 980915 Meeting with Util & Contractor Polestar Applied Technology,Inc in Rockville,Md Re Revised Accident Source Term for Perry Pilot Plant Review.List of Meeting Participants & Nonproprietary Handouts Encl ML20154J3671998-10-13013 October 1998 Summary of 980910 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md Re Licensee Proposed Changes to Design & Licensing Basis to Containment Isolation Provisions for Feedwater System.List of Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20141E7701997-05-14014 May 1997 Summary of 970508 Meeting W/Cei in Rockville,Md Re Priorities & Schedules of Licensing Issues for Plant,Unit 1. List of Meeting Attendees & Meeting Handout Encl ML20140H4881997-05-0707 May 1997 Provides Summary of 970401 Telcon Between NRC & BWROG Re Topical Rept NEDC-31858P,Rev 2, BWROG Rept for Increasing MSIV Leakage Rate Limits & Elimination of Leakage Control Sys ML20138D9441997-04-23023 April 1997 Summary of 970324 Meeting W/Licensee in Rockville,Md Re ECCS suction-strainer Program for Perry Npp,Unit 1.List of Attendees & Viewgraphs Encl 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 ML20147A7261997-01-22022 January 1997 Summary of 960910 Meeting W/Util in Rockville,Md to Discuss Revised Eal.List of Attendees Encl ML20062J8701993-11-0808 November 1993 Summary of 931028 Meeting W/Licensee in Rockville,Md Re Licensee Presentation of Summary of Plant Course of Action Plan to NRC Mgt ML20057F1271993-10-0505 October 1993 Summary of 930902 Meeting W/Util in Rockville,Md Re NRC 930405 Safety Evaluation of Rev 3 to IST Program.List of Attendees 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 ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20206D7761988-11-0808 November 1988 Summary of 881102 Meeting W/Util in Rockville,Md Re Facility Operating Performance.External Performance Assessments, Performance Indicators,Mgt Initiatives & Feedback Effectivness Discussed.Agenda & Viewgraphs Encl ML20207N9071988-10-12012 October 1988 Summary of 881006 Meeting W/Licensee & GE Re Forthcoming Reload Submittal for Feb 1989 Reload.Attendees List & Nonproprietary Slides Presented by GE Outlining Scope of Reload Application to Be Submitted by Nov 1988 Encl ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20150D7171988-07-0707 July 1988 Summary of Operating Reactors Events Meeting 88-26 on 880628 ML20153B0281988-06-22022 June 1988 Summary of Operating Reactors Events Meeting 88-25 on 880621.List of Attendees,Discussion of Significant Elements of Events & Summary of Reactor Scrams 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 ML20153G5481988-05-0404 May 1988 Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20239A0231987-09-10010 September 1987 Summary of Operating Reactor Events Meeting 87-30 on 870908, Re Briefing Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870825 Meeting.Attendees List,Summary of Reactor Scrams & Viewgraphs Encl ML20207A5221987-05-15015 May 1987 Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20204E5421987-03-19019 March 1987 Summary of Operating Reactors Events Meeting 87-06 on 870309.List of Attendees & Events Discussed & Significant Elements of Events Presented Encl ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20215D0631986-12-11011 December 1986 Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed 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 ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20215D9171986-10-0606 October 1986 Summary of 860929 Operating Reactors Events Meeting 86-34 Re Events Since Last Meeting on 860922.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Viewgraphs Encl ML20210C4211986-09-11011 September 1986 Summary of Operating Reactors Events Meeting 86-31 on 860908.Lists of Attendees,Events & Significant Elements & Assignments Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20199L5241986-06-30030 June 1986 Summary of 860611 Meeting W/Util,Usgs,Weston Geophysical, Shaw-Pittman Assoc,Geosciences Svcs,Univ of South Carolina, Gilbert Commonwealth Assoc & Nts Engineering Re Completion of Earthquake Confirmatory Items in Sser 9 ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20198D5391986-05-12012 May 1986 Summary of 860430 Meeting W/Util,Nts Engineering,Usgs, Gilbert Commonwealth,Weston Geophysical,Geoscience Svcs & Univ of South Carolina Re Earthquake Confirmatory Work Required in Sser 9.Attendance List Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20204A1371986-05-0505 May 1986 Summary of 860418 Meetings W/Usgs & Util Re Progress on Geology/Seismology Confirmatory Issues for Plants.Attendance List Encl 1999-08-04
[Table view] |
Text
.g p q&
UNITED STATES h_ g/tg
, g j NUCLEAR REGULATORY COMMISSION
, p $ WASHINGTON, D.C. 20066-0001 l
k % , * ,o December 15, 1998 ,
LICENSEE: Cleveland Electric illuminating Company l FACILITY: Perry Nuclear Power Plant, Unit No.1 l
SUBJECT:
SUMMARY
OF NOVEMBER 19,1998 MEETING ON FEEDWATER ISOLATION l
PROVISIONS '
On November 19,1998, NRC staff met with representatives of Cleveland Electric illuminating Company (CEI)in Rockville, Maryland. The purpose of the meeting was to discuss proposed changes to the design and licensing basis of the contair. ment isolation provisions for the feedwater system. A list of the meeting participants is included as Enclosure 1. The meeting handouts are included in Enclosure 2.
l Isolation provisions for the feedwater penetrations take credit for three isolation valves. Two piston lift check valves are located immediately inside and outside of the containment penetration. A third, motor-operated gate valve is loccted further upstream, outside of ;
containment. The current licensing basis relies on a water seal provided by the feedw ster leakage control system (FWLCS). The FWLCS injects water between the two check i alves and also between the outside check valve and gate valve. Due to the need for operator action to initiate this system and the time to fill the piping volume between the valves, the water seal will not be provided until approximately one hour following the postulated accident. In addition, for I long-term isolation provisions for a postulated feedwater line break inside containment, reliance is placed upon the motor-operated gate valve to close.
The feedwater check valves have typically failed to pass the local leak rate tests required by 10 CFR 50, Appendix J. As a result, the licensee has expended considerable resources in terms of both dollars and man-rems to refurbish these valves during outages. The licensee's submittal of September 9,1998, proposed changes to the design and licensing basis for the isolation provisions of the feedwater system. These changes included: 1) elimination of the feedwater check valves from the USAR listing of containment isolation valves; 2) elimination of local leak rate tests for the feedwater check valves; 3) performance of periodic boroscopic examination of the feedwater check valve seats to ensure functional operability; 4) rerouting of the feedwater leakage control system to inject into the stem of the motor-operated gate valves; and 5) introducing a second electrical supply to the motor-operated gate valves. The licensee stated that these changes would represent improvements to the currently approved containment isolation provisions.
The licensee and staff have different opinions regarding the current licensing basis for the feedwater isolation provisions. As described in the licensee's submittal of September 9,1998, the licensee considers the licensing basis to only include a single barrier (i.e., the motor-
- operated gate valve). This is due, in part, to the staffs agreement that check valve leakage will l
not contribute to offsite accident source; the only contnoutor to the accident source from the feedwater lines is water leakage past the gate valves. In addition, the lic'ensee interprets Supplement 7 to the Perry Safety Evaluation Report (NUREG-0887) as thd staffs conclusion that the gate valve will not fail to close; whereas, the staff considers the licensing basis to g 1 i f. b d 'g 9012230131 981215 DR ADGCK0500gO ,
bOdumeu i
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1
- 2 include the three valves discussed above along with the water seal. This difference in opinion .
was not resolved. l The staff noted that a single,100% reliable isolation barrier would be precedent setting and would conflict with the requirements of General Design Criterion 56. The staff further stated that !
it is not their intent to assume any containment isolation barrier to have 100% reliability and thus, not be subject to a single active failure. The staff believes that the licensee's request will require exemptions from both GDC 56 and the local leak rate testing requirements of Appendix J to 10 1 CFR 50. l The staff questioned the licensee's proposal to terminate local leak rate testing of the feedwater check valves. The licensee has established a 1 gpm leakage rate limit on the feedwater check valves and, as discussed above, Pese valves typically fail their "as-found" local leak rate tests.
As-found leakage values are typically on the order of 10 gpm. The staff questioned the failure mode and whether the leakage rates would further deteriorate over time if local leak rate testing ,
was not performed. When the licensee indicated that visualinspection of the "as found" !
condition did not identify any apparent signs of degradation, the staff questioned the value of performing boroscopic e.aminations of the check valve seats. j The staff voiced its concern about maintaining a water seal in the feedwater piping. Failure to l maintain a water seal would establish an air leakage path thus mandating pneumatic testing of the check valves. The staff questioned whether increasing the leakage limits for the check valves above 1 gpm would be beneficial. The licensee stated that the leakage control system piping is small and that flow is nearly choked. Therefore, increasing flow rates is not a practical solution. i Discussion focused on the link between containment isolation and offsite dose limits. The source of water for the feedwater leakage control system is the suppression pool which may be highly contaminated following an accident. The licensee stated that if the gate valve failed to close, check valve leakage past the gate valve could potentially result in an unacceptable offsite dose. However, since the licensee believes that the licensing basis assumes the gate valves will close, leakage rates of the check valves are not important since they don't contribute to dose. In this regard, the licensee contends that the check valves are not necessary for containment isolation.
The staff concluded that the licensee's proposal was r ot acceptable. The staff cited 1) a conflict l between a single isolation barrier and GDC 56; 2) a conflict between elimination of the local leak l- rate testing of the feedwater check valves and Appendix J to 10 CFR 50; and 3) rerouting of the i feedwater leakage control system would create an air leakage path through the check valves that would not be tested.
The staff recognized the generic problems that the BWR6/ Mark Ill owners are having with local leak rate testing of feedwater check valves. Therefore, the staff suggested the licensee i consider submitting a one-time scheduler exemption from the local leak rate testing j requirements of Appendix J for their April 1999 refueling outage. This would provide the staff L with an appropriate time frame to address the problem generically. Any exemption request l would need to ensure that the water seal was maintained, include a cost / benefit analysis, and l
l
- 3 12/15/98 l l be risk informed. The risk study would need to address the impact of not testing the feedwater l check valves and the probability that the gate valves would not close.
The staff stressed that any long term solution would require a second isolation barrier. The licensee stated that the next system valve upstream of the gate valve would be located outside .
i of the steam tunnel in the turbine building. Questions regarding missile protection and seismic '
class were discussed.
! in cor.clusion, both the staff and the licensee stated a need to address this issue at their next, !
respective management level. When asked if the licensee would prefer to modify their existing submittal or receive a formal denial of the existing submittal, the licensee said they would contact us. l Original signed by:
1 Douglas V. Pickett, Senior Project Manager Project Directorate 111-2 Division of Reactor Projects Ill/IV l
Office of Nuclear Reactor Regulation l Docket No. 50-440
Enclosures:
List of Meeting Participants Meeting Handouts cc w/encls: See next page DISTRIBUTION:
Hard Coov w/encls E-mail w/Enct 1 Docket File SCollins (SJC1) 'JKudrick EAdensam PD lll-2 Reading RZimmerman EThrom PUBLIC THiltz CBerlinger.
GGrant, Rlli BBoger GHolahan Hard Coov w/ Encl 1 OGC ACRS DOCUMENT NAME: G:\ PERRY \MTG11_19. SUM l Ta receive e copy of this document, indicate in the box: *C" = Copy without enclosures *E' = Copy with enclosures "N" = No copy j
OFFICE PM:PI)LI)g? LA:PDIII-2 6T D:PDIII-2 C, .
BC:SCSB ,
NAME' DPiclTth ' EBarnhill 2 F SRichards 5/EV CBerlinger('/Jh DATE 12/9 /98 12/ 7 /98 12/rd/98 12/9 /98 bil2/ /98 0FFICIAL RECORD COPY !
l l l
l l
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3 12/15/98 j ' be risk informed. The risk study would need to address the impact of not testing the feedwater check valves and the probability that the gate valves would not close.
The staff stressed that any long term solution would require a second isolation barrier. The licensee stat 3d that the next system valve upstream of the gate valve would be located outside of the steam tunnel in the turbine building. Questions regarding missile protection and seismic class were discussed.
l In conclusion, both the staff and the licensee stated a need to address this issue at their next,
- respective management level. When asked if the licensee would prefer to modify their existing submittal or receive a formal denial of the existing submittal, the licensee said they would contact us.
Original signed by:
Douglas V. Pickett, Senior Project Manager i Project Directorate lll-2 !
Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-440 ,
Enclosures:
List of Meeting Participants Meeting Handouts i
- cc w/encis
- See next page DISTRIBUTION:
= Hard Coov w/encls E-mail w/Enct 1 Docket File . SCollins (SJC1) JKudrick . EAdensam PD lll-2 Reading RZimmerman EThrom PUBLIC ' THiltz .,CBerlinger l GGrant, Rlil BBoger - GHolahan Hard Coov w/ Encl 1
)
OGC ACRS
. DOCUMENT NAME: G:\ PERRY \MTG11 19. SUM Ta receive a copy of this document, indcate in 'the box: "C" = Copy without enclosures ~ "E" = Copy with enclosures "N" = No copy 0FFICE PM:RDillt2 LA:PDIII-2 7 D:PDIII-2 C BC:SCSB ,
NAME DPiclCd'th ' EBarnhill W SRichards 54V CBerlingerf '#f$
DATE 12/ 9 /98 12/ 7 /98 12/l'l/98 12/9 /98 F12/ /98 OFFICIAL RECORD COPY 9
1 *=61- T- e W:
u
- 3 be risk informed. The risk study would need to address the impact of not testing the feedwater check valves and the probability that the gate valves would not close.
The staff stressed that any long term solution would require a second isolation barrier. The licensee stated that the next system valve upstream of the gate valve would be located outside of the steam tunnelin the turbine building. Questions regarding missile protection and seismic class were discussed.
In conclusion, both the staff and the licensee stated a need to address this issue at their next, respective management level. When asked if the licensee would prefer to modify their existing submittal or receive a formal denial of the existing submittal, the licensee said they would contact us. '
Q v PM Douglas V. Pickett, Senior Project Manager Project Directorate lll-2 Division of Reactor Projects Ill/IV ;
Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
List of Meeting Participants ;
Meeting Handouts cc w/encls: See next page b
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' C:nt:rior S rvice Company PIrry Nucl3ar Pow:r Plant, Units 1 and 2 cc:
Mary E. O'Reilly James R. Williams FirstEnergy - A290 Chief of Staff 10 Center Road Ohio Emergency Management Agency Perry, OH 44081 2855 West Dublin Granville Road Columbus, OH 43235-2206 Resident inspector's Office U.S. Nuclear Regulatory Commission Donna Owens, Director P.O. Box 331 Ohio Department of Commerce Perry, OH 44081-0331 Division of Industrial Compliance Bureau of Operations & Maintenance Regional Administrator, Region ill 6606 Tusr/ng Road U.S. Nuclear Regulatory Commission P.O. Box 4009 801 Warrenville Road Reynoldsburg, OH 43068-9009 Lisle, IL 60532-4531 Mayor, Villagd of North Perry Sue Hiatt North Perry Village Hall OCRE Interim Representative 4778 Lockwood Road 8275 Munson North Perry Village, OH 44081 Mentor, OH 44060 Radiological Health Program Henry L. Hegrat Ohio Department of Health Regulatory Affairs Manager P.O. Box 118 Cleveland Electric illuminating Co. Columbus, OH 43266-0118 Perry Nuclear Power Plant P.O. Box 97, A210 Ohio Environmental Protection Perry, OH 44081 Agency DERR-Compliance Unit Lew W. Myers ATTN: Mr. Zack A. Clayton Vice President - Nuclear, Perry P.O. Box 1049 Centerior Service Company Columbus, OH 43266-0149 P.O. Box 97, A200-Perry, OH 44081 Chairman Perry Township Board of Trustees Mayor, Village of Perry 3750 Center Road, Box 65 4203 Harper Street Perry, OH 44081 Perry, OH 44081 State of Ohio FirstEnergy Corporation Public Utilities Commission Michael Beiting East Broad Street Associate General Counsel Columbus, OH 43266-0573 76 S. Main Akron, OH 44308 William R. Kanda, Jr., Plant Manager Cleveland Electric illuminating Co.
Perry Nuclear Power Plant P.O. Box 97., SB306 Perry, OH 44081
MEETING ATTENDEES NRC AND CLEVELAND ELECTRIC ILLUMINATING COMPANY l
FEEDWATER ISOLATION PROVISIONS NOVEMBER 19,1998 i
CLEVELAND ELECTRIC ILLUMINATING CO.
Robert W. Schrauder Henry L. Hegrat Bradley S. Ferrell Cal Heintz !
Richard Dame Thomas Shega SCIENTECH - NUS Dave Studley Nfl0 Carl Berlinger Jack Kudrick Ed Throm Stuart Richards
. Doug Pickett Lawrence Burkhart ILLINOIS POWER COMPANY Dur; Korneman Enclosure 1
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l Wh hT22 u, Perry Nuclear Power Plant
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Feedwater Penetration l
ImprovementDuringRFO7 l
NRCMeeting November 19,1998 5
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PageI E gauCSO R.1:.i 7
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Feedwater Penetration Improvement
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- * - . g_ g 7,-,gy e ,g - - '4 e Meeting Goal: to provide information to
! support NRC approval of the amendment
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Project Goal: to improve the overall j
performance of the Feedwater Penetrations
- Reduce actual dose to plant workers .
j Improve protection of the public i
Provide a risk-informed level of protection to
- achieve the above goals t
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l l Feedwater Penetration Improvement l Current Configuration:
Gate valve seats have been very leak tight - no rework 1
Offsite doses are mitigated by closure of the gate
) valves (licensing post-LOCA dose cales only consider j the gate valve leakage, not the checks) ,
) -
Check valve leakage criteria of < 1 gpm is required to i meet the current FWLCS design function of filling the pipe within one hour, not for dose cale reasons ,
i j -
Workers were exposed to > 5 rem to work on the
].
4 check valve seats in RFO6; plus dose from testing Page 3
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'M Feedwater Penetration Improvement s* E < we.e6wi E'A E "wawe e .4 e*=^
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l Benefits of new design l Improves the probability of the Feedwater lines
- getting a water seal within the currently licensed i
period of time after a LOCA due to relocated FWLCS Improves the probability of closure of the currently l licensed high integrity gate valves, after a LOCA/ LOOP /Div.1 failure, due to new provisions for an alternate power supply
>> Reduces the dose received by workers who have been performing maintenance and testing of the checks -
>> Proposal continues to provide protection for a postulated Feedwater Line Break Outside Containment Page 4
i Feedwater Penetration Improvement l
3 Other options considered
- >> Add Soft-seats to the Check Valves, and j maintain the current licensing basis l Maintain current FWLCS injection point, and 1
increase allowable Check Valve leakage -
l Design & install a new " sister" gate valve in each line i >> Many other options were also considered
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Feedwater Penetration Improvement
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l Other Options Considered (continued) i Add Soft-seats to the Check Valves, and i maintain the current licensing basis l >> Still would need to test checks, and would need to j replace seats each refuel outage due to EQ l .
l Still would see leakage > 1 gpm (EPRI) l
>> Wouldn't have the extra recovery time for actuation of
- FWLCS i
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- Feedwater Penetration Improvement
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Other Options Considered (continued)
Maintain current FWLCS injection point, and l
increase allowable Check Valve leakage
! Would not be able to get enough FWLCS flow into the
- pipe (would require installation of new, larger diameter ,
l Class 1 connections to pass the flow in order to fill the pipe l within an hour, which is not feasible due to the design of l the penetration and of the valves) i 4
>> Still would need to test checks i Would have potential for releasing post LOCA l -
suppression pool (FWLCS) water from containment .
! Using outside clean water source would flood containment Page 7
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! Feedwater Penetration Improvement
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! Other Options Considered (continued) l Design & install a new gate valve in each line Still would need to test checks l Would provide very little benefit to the post-LOCA l reliability of the penetration as compared to the i proposed change (proposed change will provide an -
l alternate power supply to the existing gate valves)
- >> Would not factor in to the analysis of the Feedwater line l break outside containment
] >> Would be a high dose job, and extremely expensive i
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>> The cost-benefit ratio does not justify this change
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Feedwater Penetration Improvement l
FirstEnergy Docketed Letter Contents l
Provide design summary of alternate power supply Provide results of operator action review
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Provide results of th'e dose cale sensitivity analysis Provide results of a risk-informed review on the proposed License Amendment -
Provide several updated USAR pages Add page from Table 3.2-1 NOTES about the third valve with high leak tight integrity.
) Revise page describing fill time on the bonnet, and adding the word "approximately".
Editorial change to cross out words that should have been crossed out in the first submittal.
l Revise page describing "both" subsystems being interlocked, to show that only one is interlocked.
] n Add page from "Feedwater Line Break Outside Containment", describing dose calc result, to show the
- impact of check valve leakage on the cale (showing it remains bounded by the Main Steam Line Break Outside Containment calc).
Ie Page 9 l . . ..
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