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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20058N4941993-12-15015 December 1993 Summary of 931130 Meeting W/Sce&G in Rockville,Md Re Licensee Upcoming SG Replacement,Scheduled to Begin Sept 1994.List of Attendees Encl ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057B9321993-09-20020 September 1993 Summary of 930727 Meeting W/Util & Westinghouse Re Results Analysis of Three Tubes Pulled Form Unit 1 B SG During Last RF7.List of Meeting Attendees & Meeting Handouts Encl ML20128C7481993-01-28028 January 1993 Summary of Operating Reactors Events Meeting 93-03 on 930127.List of Attendees & Elements Discussed Encl ML20058G4341990-10-31031 October 1990 Summary of 901016 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Actions for Facility ML20055G8671990-07-19019 July 1990 Summary of 900709 Meeting W/Util to Discuss Status of Licensing Issues.List of Attendees & Viewgraphs Encl 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 ML20246B9571989-08-15015 August 1989 Summary of 890801 Meeting W/Util in Rockville,Md Re Loss of Offsite Power Event at Plant.List of Attendees,Agenda & Handouts Encl ML20247E7021989-07-21021 July 1989 Summary of 890621 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Plant.Discusses Possibility of Next Refueling Outage Being Moved from Mar 1990 to Fall 1990 ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20246M9241989-05-0808 May 1989 Summary of 890418 & 19 Meetings W/Region II & Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Handouts Encl ML20248E9911989-04-0404 April 1989 Summary of 890322 Meeting W/Util in Rockville,Md to Discuss Resin Intrusion Into Condensers at Plant.Licensee Requested to Provide Commitment to Evaluate Procedures Involving Steam Generator Tube Rupture Event.Viewgraphs Encl ML20245J2111989-02-28028 February 1989 Summary of 890207 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl ML20196C7851988-12-0505 December 1988 Summary of 881129 Meeting W/Util in Atlanta,Ga Re Status of Licensing Issues for Facility.List of Attendees Encl & Related Info Encl ML20195C6971988-10-28028 October 1988 Summary of 881018 Meeting W/Util Re Status of Licensing Issues for Plant.List of Attendees Encl ML20204B3111988-10-14014 October 1988 Summary of 881006 Meeting W/Util in Rockville,Md Re Util Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20154Q2061988-09-28028 September 1988 Summary of 880921 Meeting W/Util & Gilbert/Commonwealth Assoc in Rockville,Md Re Proposed Change to Tech Spec 3.6.1.6, Containment Structural Integrity ML20154Q0571988-09-28028 September 1988 Summary of 880901 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl ML20154M4281988-09-20020 September 1988 Summary of 880817 Meeting W/Util in Rockville,Md to Discuss Removal of Fire Protection Tech Specs for Facility & Recent Issuance of Generic Ltr 88-12.Attendance List & Supporting Documentation Encl ML20151D2731988-07-14014 July 1988 Summary of 880628 Meeting W/Util at Facility Re Status of Licensing Issues for Facility.List of Attendees & Handout Providing Current Assessment of Status of Various Licensing Actions Encl ML20195B4691988-06-0606 June 1988 Summary of 880524 Meeting W/Util in Rockville,Md to Discuss Proposed Change to Tech Spec 3.6.1.6, Containment Structural Integrity. Related Info Encl ML20151S7041988-04-22022 April 1988 Summary of 880412 Meeting W/Util in Atlanta,Ga,To Discuss Status of Licensing Issues.List of Attendees,Agenda,Status of TACs & Proposed Tech Specs Encl ML20147E0751988-02-29029 February 1988 Summary of 880217 Meeting W/Util in Rockville,Md Re Status of Current & Future Licensing Actions for Facility.Attendees List,Agenda & Handouts Encl ML20196G0491988-02-29029 February 1988 Summary of 871202 & 03 Meetings W/Util Re Status of Current & Future Licensing Actions for Plant.List of Attendees,Viewgraphs & Related Info Encl ML20236S2911987-11-23023 November 1987 Summary of 871105 & 06 Meetings W/Util,Westinghouse & Comex at Plant & Nuclear Training Ctr Re Audit of Spds.Attendee List & Presentation Matl Encl ML20245C9791987-11-0202 November 1987 Summary of 870929 Meeting W/Util in Atlanta,Ga Re Status of Current & Future Licensing Items.List of Attendees & Status List Encl ML20245C9281987-11-0202 November 1987 Summary of 870805 Meeting W/Util Re Site Tour & Discussion of Technical Issues.List of Attendees,Agenda & Viewgraphs Encl ML20214Q1761987-05-29029 May 1987 Summary of 870518 Meeting W/Util Re NRC Reorganization Concerning Philosophy & Implementation.Status of Current & Future Licensing Items Also Reviewed.Lists of Attendees & Status of Licensing Items Encl ML20206K5011987-04-15015 April 1987 Summary of 870326 Meeting W/Util in Bethesda,Md to Discuss Status of Licensing Actions,Length of Refueling Outage, Upcoming NRC Reorganization & Plant Status ML20205A5801987-03-23023 March 1987 Summary of 870305 Meeting W/Util in Bethesda,Md Re Priority of Licensing Actions for Upcoming Refueling Outage,Length of Refueling Outage & Upcoming NRC Reorganization.Attendees List Encl ML20210S8711987-02-0404 February 1987 Summary of 870127 Meeting W/Util in Bethesda,Md Re Status of Licensing Action for Facility,Including Licensee Approach to Maintaining Steam Generator Integrity & Amends Needed for Refueling Commencing in Mar 1987.List of Attendees Encl ML20210B0351986-09-15015 September 1986 Summary of 860808 Meeting W/Licensee in Bethesda,Md Re Relative Priority & Status of Licensing Actions for CY86 & Util Approach to Maintaining Steam Generator Integrity. Attendee List Encl ML20204G5781986-07-31031 July 1986 Summary of 860627 Meeting W/Utils & Westinghouse in Bethesda,Md to Discuss P-star Analysis for Steam Generators at Facility.List of Attendees & Viewgraphs Encl ML20206E5671986-06-17017 June 1986 Summary of 860612 Meeting W/Util in Bethesda,Md Re Submitted & Proposed Licensing Action,Priorities for Calendar Yr & Steam Generator & Containment Structural Integrity ML20198B4371986-05-16016 May 1986 Summary of 860508 Meeting W/Util in Bethesda,Md to Discuss NRC Re Status of Generic Issues & Priority of Licensing Actions for 1986.Attendee List Encl ML20141F5081986-04-11011 April 1986 Summary of 860402 Meeting W/Util & Gilbert/Commonwealth,Inc in Bethesda,Md Re Fire Protection Items,Including Temp Indication for Reactor Coolant Loop & Deviations Identified in Util .Attendees List & Viewgraphs Encl ML20210K0661986-03-31031 March 1986 Summary of 860321 Meeting W/Util in Bethesda,Md Re Status of Licensing Actions.List of Attendees & Submitted & Proposed Licensing Actions Encl ML20141D1251986-03-31031 March 1986 Summary of 860205 Meeting W/Util at Site to Discuss Mgt Philosophy Re Spent Fuel Storage & Containment Tendon Surveillance & Tour Plant ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20133F9941985-10-0707 October 1985 Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl ML20134K8391985-08-12012 August 1985 Trip Rept of 850722 & 23 Site Visits Re Evaluation of Contributing Factors to 850221 Event & Util Internally Recommended Corrections ML20134F2551985-07-31031 July 1985 Summary of 850724-25 Meetings W/Util,In Gilbert/Commonwealth & Interscience Consultants in Bethesda,Md Re Util Fire Protection Reevaluation Program.Fire Protection Program Summary Encl ML20127D1571985-06-13013 June 1985 Summary of 850530 Operating Reactor Events Meeting to Brief Ofc Director,Div Directors & Representatives on Events Since 850515 Meeting.List of Attendees,Viewgraphs & Status of Assignments Encl 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 ML20062B2091982-07-23023 July 1982 Summary of 820721 Meeting W/Westinghouse,Anl,Bechtel,Tsi, Cnasco & Utils in Bethesda,Md Re Progress in Resolving Accelerated Tube Wear at Operating Plants W/Westinghouse Model D Steam Generators 1993-09-20
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20058N4941993-12-15015 December 1993 Summary of 931130 Meeting W/Sce&G in Rockville,Md Re Licensee Upcoming SG Replacement,Scheduled to Begin Sept 1994.List of Attendees Encl ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057B9321993-09-20020 September 1993 Summary of 930727 Meeting W/Util & Westinghouse Re Results Analysis of Three Tubes Pulled Form Unit 1 B SG During Last RF7.List of Meeting Attendees & Meeting Handouts Encl ML20128C7481993-01-28028 January 1993 Summary of Operating Reactors Events Meeting 93-03 on 930127.List of Attendees & Elements Discussed Encl ML20058G4341990-10-31031 October 1990 Summary of 901016 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Actions for Facility ML20055G8671990-07-19019 July 1990 Summary of 900709 Meeting W/Util to Discuss Status of Licensing Issues.List of Attendees & Viewgraphs Encl 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 ML20246B9571989-08-15015 August 1989 Summary of 890801 Meeting W/Util in Rockville,Md Re Loss of Offsite Power Event at Plant.List of Attendees,Agenda & Handouts Encl ML20247E7021989-07-21021 July 1989 Summary of 890621 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Plant.Discusses Possibility of Next Refueling Outage Being Moved from Mar 1990 to Fall 1990 ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20246M9241989-05-0808 May 1989 Summary of 890418 & 19 Meetings W/Region II & Util to Discuss Status of Licensing Issues for Plant.List of Attendees & Handouts Encl ML20248E9911989-04-0404 April 1989 Summary of 890322 Meeting W/Util in Rockville,Md to Discuss Resin Intrusion Into Condensers at Plant.Licensee Requested to Provide Commitment to Evaluate Procedures Involving Steam Generator Tube Rupture Event.Viewgraphs Encl ML20245J2111989-02-28028 February 1989 Summary of 890207 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl ML20196C7851988-12-0505 December 1988 Summary of 881129 Meeting W/Util in Atlanta,Ga Re Status of Licensing Issues for Facility.List of Attendees Encl & Related Info Encl ML20195C6971988-10-28028 October 1988 Summary of 881018 Meeting W/Util Re Status of Licensing Issues for Plant.List of Attendees Encl ML20204B3111988-10-14014 October 1988 Summary of 881006 Meeting W/Util in Rockville,Md Re Util Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20154Q0571988-09-28028 September 1988 Summary of 880901 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Facility.List of Attendees & Handouts Encl ML20154Q2061988-09-28028 September 1988 Summary of 880921 Meeting W/Util & Gilbert/Commonwealth Assoc in Rockville,Md Re Proposed Change to Tech Spec 3.6.1.6, Containment Structural Integrity ML20154M4281988-09-20020 September 1988 Summary of 880817 Meeting W/Util in Rockville,Md to Discuss Removal of Fire Protection Tech Specs for Facility & Recent Issuance of Generic Ltr 88-12.Attendance List & Supporting Documentation Encl ML20151D2731988-07-14014 July 1988 Summary of 880628 Meeting W/Util at Facility Re Status of Licensing Issues for Facility.List of Attendees & Handout Providing Current Assessment of Status of Various Licensing Actions Encl ML20195B4691988-06-0606 June 1988 Summary of 880524 Meeting W/Util in Rockville,Md to Discuss Proposed Change to Tech Spec 3.6.1.6, Containment Structural Integrity. Related Info Encl ML20151S7041988-04-22022 April 1988 Summary of 880412 Meeting W/Util in Atlanta,Ga,To Discuss Status of Licensing Issues.List of Attendees,Agenda,Status of TACs & Proposed Tech Specs Encl ML20147E0751988-02-29029 February 1988 Summary of 880217 Meeting W/Util in Rockville,Md Re Status of Current & Future Licensing Actions for Facility.Attendees List,Agenda & Handouts Encl ML20196G0491988-02-29029 February 1988 Summary of 871202 & 03 Meetings W/Util Re Status of Current & Future Licensing Actions for Plant.List of Attendees,Viewgraphs & Related Info Encl ML20236S2911987-11-23023 November 1987 Summary of 871105 & 06 Meetings W/Util,Westinghouse & Comex at Plant & Nuclear Training Ctr Re Audit of Spds.Attendee List & Presentation Matl Encl ML20245C9791987-11-0202 November 1987 Summary of 870929 Meeting W/Util in Atlanta,Ga Re Status of Current & Future Licensing Items.List of Attendees & Status List Encl ML20245C9281987-11-0202 November 1987 Summary of 870805 Meeting W/Util Re Site Tour & Discussion of Technical Issues.List of Attendees,Agenda & Viewgraphs Encl ML20214Q1761987-05-29029 May 1987 Summary of 870518 Meeting W/Util Re NRC Reorganization Concerning Philosophy & Implementation.Status of Current & Future Licensing Items Also Reviewed.Lists of Attendees & Status of Licensing Items Encl ML20206K5011987-04-15015 April 1987 Summary of 870326 Meeting W/Util in Bethesda,Md to Discuss Status of Licensing Actions,Length of Refueling Outage, Upcoming NRC Reorganization & Plant Status ML20205A5801987-03-23023 March 1987 Summary of 870305 Meeting W/Util in Bethesda,Md Re Priority of Licensing Actions for Upcoming Refueling Outage,Length of Refueling Outage & Upcoming NRC Reorganization.Attendees List Encl ML20210S8711987-02-0404 February 1987 Summary of 870127 Meeting W/Util in Bethesda,Md Re Status of Licensing Action for Facility,Including Licensee Approach to Maintaining Steam Generator Integrity & Amends Needed for Refueling Commencing in Mar 1987.List of Attendees Encl ML20210B0351986-09-15015 September 1986 Summary of 860808 Meeting W/Licensee in Bethesda,Md Re Relative Priority & Status of Licensing Actions for CY86 & Util Approach to Maintaining Steam Generator Integrity. Attendee List Encl ML20204G5781986-07-31031 July 1986 Summary of 860627 Meeting W/Utils & Westinghouse in Bethesda,Md to Discuss P-star Analysis for Steam Generators at Facility.List of Attendees & Viewgraphs Encl ML20206E5671986-06-17017 June 1986 Summary of 860612 Meeting W/Util in Bethesda,Md Re Submitted & Proposed Licensing Action,Priorities for Calendar Yr & Steam Generator & Containment Structural Integrity ML20198B4371986-05-16016 May 1986 Summary of 860508 Meeting W/Util in Bethesda,Md to Discuss NRC Re Status of Generic Issues & Priority of Licensing Actions for 1986.Attendee List Encl ML20141F5081986-04-11011 April 1986 Summary of 860402 Meeting W/Util & Gilbert/Commonwealth,Inc in Bethesda,Md Re Fire Protection Items,Including Temp Indication for Reactor Coolant Loop & Deviations Identified in Util .Attendees List & Viewgraphs Encl ML20210K0661986-03-31031 March 1986 Summary of 860321 Meeting W/Util in Bethesda,Md Re Status of Licensing Actions.List of Attendees & Submitted & Proposed Licensing Actions Encl ML20141D1251986-03-31031 March 1986 Summary of 860205 Meeting W/Util at Site to Discuss Mgt Philosophy Re Spent Fuel Storage & Containment Tendon Surveillance & Tour Plant ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20133F9941985-10-0707 October 1985 Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl ML20134F2551985-07-31031 July 1985 Summary of 850724-25 Meetings W/Util,In Gilbert/Commonwealth & Interscience Consultants in Bethesda,Md Re Util Fire Protection Reevaluation Program.Fire Protection Program Summary Encl ML20127D1571985-06-13013 June 1985 Summary of 850530 Operating Reactor Events Meeting to Brief Ofc Director,Div Directors & Representatives on Events Since 850515 Meeting.List of Attendees,Viewgraphs & Status of Assignments Encl 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 ML20062B2091982-07-23023 July 1982 Summary of 820721 Meeting W/Westinghouse,Anl,Bechtel,Tsi, Cnasco & Utils in Bethesda,Md Re Progress in Resolving Accelerated Tube Wear at Operating Plants W/Westinghouse Model D Steam Generators 1993-09-20
[Table view] |
Text
1 July 31,1986 1
Docket No. 50-395 LICENSEE: South Carolina Electric & Gas Company FACILITY: V. C. Summer Nuclear Station
SUBJECT:
SUMMARY
OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL On June 27, 1986, the NRC staff met with the South Carolina Electric and Gas Company (SCEF.G) to discuss the P-Star analysis for steam generators at the V. C. Summer Nuclear Station. The meeting was held in Bethesda, Maryland.
A list of those persons who attended the meeting is included as Enclosure 1.
DISCUSSION Attached as Enclosure 2 is the meeting agenda and non-proprietary viewgraphs shown during the meeting. The main topic of discussion was the definition of an intact tube. The utility agreed to submitt infomation regarding inspection of repaired tubes and the NRC staff agreed to review in more depth the analysis regarding friction retaining a tube in the tubesheet.
S Jon B. Hopkins, Project Manager PWR Project Directorate #2 Division of PWR Licensing-A
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION:
-Docket File OGC JHopkins EJordan NRC PDR BGrimes Local PDR ACRS (10)
PWRf2 Reading NRC Participants JPartlow LRubenstein AD#2 mPe,,a a P pkins LRuhe te,n 07Q86 'j 07 /86 07/31/86 8600070333 PDR 860731 ADOCK 05000395 PDR
ENCLOSURE 1 MEETING ATTENDEES June 27, 1986 NRC SCF8G ult 6pkins PTr67 DSellers Testes ESullivan DMalkmus CCheng APaglia JMuscara JRajan l
WESTINGHOUSE DUKE POWER COMPANY RKeating DMayes g
MProviano JDay CHirst GWhiteman JEsposito t
l
. _,_.w.y,, - --- ' - * ~ " " -- ~ - ' ' ' '
s ENCLOSURE 2 NRC, MEETING TUBE REPAIR AND P-STAR CRITERIA BETHESDA. MARYLAND -
JUNE 27. 1986 3 PRESENTATION
- 1. INTRODUCTION SCE&G.
- 2. P* 8 ASIS REVIEW WESTINGHOUSE
- 3. INTACT TU8E SCE&G/ WESTINGHOUSE
- a. Define Structural Limit -
- b. Defects Below P*
- c. Post Plugging Tube Degradation
- d. Inspection Requirements
- e. Definition
- 4. INSPECTION OF REPAIRED TUBES SCE&G
- 5. SU W RY Q SCE&G e
i
. . C s f
2 e e RJBE PLUGGING CRITERION IN THE 1UBESHEET REGIm
.e 9
'IEONICAL SPECIFICATION PLUGGING LIMIT APPLIES 1HROUGH THE TUBE IMH ACCOUNT FOR TE CONSTRAINING EFFECT OF 'IHE 1UBESHEET DEFINE A REGIm WITHIN THE 1UBESHEET IN hMICH NO PLUGGING REQUIREMENTS hTED APPLY 9
4 4
e e Tubesheet Plugging Criteria :
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Tubesheet g
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Indications need to be P. Plugged /Steeved a n '
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{
Indications need not l be Plugged / Sleeved l
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PULINT CRITERIN (P*) DEVELOPMENT BRIEF OEWIEK ASPECTS O WBE BURST h1LL NOT OCCUR h1 WIN WE 'IUBESHEET 0 WBE COL 1 APSE h'ILL NOT OCCUR k'IWIN WE WBESHEET O TECHNICAL SPECIFICATIm LEAKAGE LIMITS APPLY
-- CM SIDERATIE S 0 A FIXED OR CAP'IURED WBE END IS MAIhTAINED 0 PRIMARY 'IO-SECONDARY LEAKAGE IS LIMITED 0 *IUBE INTEGRITY IS MAIhTAINED UNDER LIMITING CmDITIES O WBE IhTEGRITY ABOVE P* IS DEKNSTRA'IED ( BY CSTIhUED ECT)
O, ,
ECT AXIAL UNCERTAlhTY
-- RESULTS O WBE PULINT IS PRECLUDED 0 'IUBES h*IW INDICATINS BELOK P* REMAIN IN SER\1CE O P* CRITERION DOES NUT APPLY TO PERIPHERAL WBES ANT)
SOE IhTERIOR WBES 1
0
Potential Location of IDSCC L
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S/G Tube
! Expansion Transition Zone N
' 1 f '
Tubesheet Eddy Current ,
Indication 4
l
- ._ . _ _ . - - - . _ _ _ _ _ _ - . . - - _ = _ _ _ _ _ --
J
- I TRE ATMENT OF TUBESHEET TUBE INDICATIONS PREMISE 1
THE BASIC PREMISE TO BE APPLIED IS THAT IF A SEVERED TUBE END IS CONSTRAINED SUCH THAT IT CANNOT BECOME CLEAR OF THE TUBESHEET THE INTEGRITY OF THE BUNDLE IS CONSERVED, AND IF LEAKAGE IS LIMITED THE SAFETY CONSEQUENCES OF LEAKAGE HAVE BEEN APPROPRIATELY ADDRESSED.
APPLICATION OF RG 1.121 IDENTIFICATION OF A DISTANCE, DESIGNATED P*, BELOW THE TOP OF THE TUBESHEET FOR WHICH TUBE DEGRADATION OF ANY. EXTENT WILL NOT RESULT IN A SEVERED TUBE END FROM BECOhDNG CLEAR OF THE TUBESHEET DURING NORMAL OR POSTULATED ACCIDENT CONDITIONS.
CONSIDERATIONS I. DEVELOPMENT OF THE ENGAGEMENT DISTANCE REQUIRED TO MAINTAIN A FIXED TUBE END CONDITION IN THE TUBESHEET WITH A POSTULATED CIRCUMFERENTIAL INDICATION.
- 2. LIMITATION OF PRIMARY-TO SECONDARY LEAKAGE CONSISTENT WITH i ACCIDENT ANALYSIS ASSUMPTIONS.
- 3. MAINTENANCE OF TUBE INTEGRITY UNDER POSTULATr.D '.IMITING CONDITIONS OF PRIMARY TO SECONDARY AND SECONDA 7 TO PRIMARY DIFFERENTIAL PRESSURE.
4
TUBESHEET EFFECTS RELATIVE TO THE PERFORMANCE OF DEGR ADED TUBES t
- BURST STRENGTH OF FULL DEPTH EXPANDED TUBES THE BURST STRENGTH OF THAT PORTION OF A TUBE LOCATED WITHIN THE TUBESHEET IS REINFORCED TO THE EXTENT THAT THE PRESENCE OF THE TUBE MATERIAL IS NOT NECESSARY,I.E., TUBE BURST IS OBVIATED BECAUSE DEFORMATION BEYOND THE EXPANDED OUTER DIAhETER IS ESSENTIALLY PRECLUDED.
- COLLAPSE STRENGTH OF FULL DEPTH EXPANDED TUBES THE COLLAPSE STRENGTH OF THAT PORTION OF THE TUBE LOCATED WITHIN THE TUBESHEET IS SIGNIFICANTLY INCREASED. COLLAPSE MODES WHICH ARE ACCOMPANIED BY LOCAL DEFORMATION BEYOND THE OUTER DIAMETER (GEOMETRICAL REACTION) ARE SIGNIFICANTLY
.RENGTHENED.
- LEAKAGE OF FULL DEPTH EXPANDED TUBES NO ACTUAL LEAKPATH IS EXPECTED DUE THE HARDROLLING OF THE TUBES INTO THE TUBESHEET. LEAK RATE EFFECTS HAVE BEEN ASSESSED BY ASSUMING A LEAK PATH TO EXI?T AND DETERMINING THE RELATIVE LEAKAGE WHICH WOULD OCCUR DURING POSTULATED ACCIDENT CONDITIONS.
5
. ~ *^ .
DEVELOPMENT OF THE P8 CRITERION
' DEVELOPMENT OF THE P* CRITERION IS BASED ON ASSUMING THAT A TUBE HAS BEEN DEGRADED TO THE POINT OF SEVERENCE WITHIN THE TUBESHEET. THE SEVERED TUBE IS POSTULATED TO MQVE UPWARD TO A POSITION WHERE THE EXTRADOS SURFACE OF THE U BEND APEX IS IN CONTACT WITH THE TUBE DIRECTLY ABOVE IT. UNDER OPERATING OR ACCIDENT CONDITIONS ADDITIONAL DISPLACEMENT MAY OCCUR.THE TOTAL AMOUNT OF UPWARD MOVEhENT HAS BEEN ADDRESSED BY THE FOLLOWING CONSIDERATIONS.
- MANUFACTURING CONSIDERATIONS ^
A STUDY OF THE FABRICATION AND ASSEMBLY PROCESS WAS CONDUCTED WHICH INCLUDED CONSIDERATION OF NOMINAL GAP DIMENSIONS AND MANUFACTURING STEPS WHICH COULD RESULT IN VARIATIONS TO THE NOMINAL DIMENSIONS. A MAXIMUM AS BUILT GAP VALUE WAS IDENTIFIED.
- THERMAL EXPANSION CONSIDERATIONS VERTICAL DISPLACEhENT OF A SEPARATED TUBE U-BEND WAS CONSIDERED TO BE THAT OF AN INTACT OUTBOARD NEIGHBOR TUBE -
U BEND.
- PRESSURE ELONGATION CONSIDERATIONS AXIAL ELONGATION OF AN INTACT OUTBOARD NEIGHBOR TUBE U BEND WAS CONSIDERED TO PERMIT ADDITIONAL UPWARD M6VEMENT OF A SEVERED TUBE U-BEND.
. 6-
. - - _ , , _ _ _ , - , , _ , - - - - - , _ _ - - - - , , , , , , ,__.y- -- , , . . -,- - , , , - ,,,_ -,
. 1. " OUTBOARD NEIGHBOR" STRUCTURAL LIMIT -
Minimum allowable wall to resist failure due loading of a postulated separated P* tube during a postulated SLB.
AXIALLY ORIENTED INDICATIONS -
Expected case if degradation occurs in the VC Summer steam generators.
Through-wall indications could exist and still' resist failure.
CIRCUHFERENTIALLY ORIENTED INDICATIONS -
Case 1 - Outboard Neighbor Plugged -
Minimum Wall thickness Normal 0.0036 inch. 8.4 %
Upset 0.0045 inch, 10.1 %
Faulted 0.0035 inch, 8.1 %
C Evenly thinned 360 degrees around circumference.
,Envelopes cracklike degradation .
Case 2 - Outboard Neighbor Active -
Minimum Will Thickness Normal 0.007 inch, 16.8 %
Upset 0.009 inch, 20.1 %
Faulted 0.007 inch, 16.3 %
Evenly thinned 360 degrees around circumference.
Includes SLB pressure differential loading.
Leak-Before-Break expected apply.
. - - - - , - ,--w-- , -%-,,,,e-,,e, ww,- -- - - - - - - - - - - - - - - , ---m---. we. - - ..- - - - -
. s i
,l.- _
- 4. ' INTACT" NEIGHBOR DEFINITION -
Indications Above3P* - Plant Technical Specification.
Currently Plugged - Considered as Intact.
Greater than 92 % for 360 Degrees - NOT Considered Intact.
Post Inspection Tube Remaining in Service - Considered Intact.
b _
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- . . _ . e , ,.y -r- -- --'--v= -P -
v 4-v vw- ----- --- =-
PLUGGED TUBE CORROSION CONSIDERATIONS O PRIMARY SIDE
- TEMPERATURE STRESS
- HYDROGEN PARTIAL PRESSURE O SECONDARY SIDE
- CONTAMINANT CONCENTRATION
- TEMPERATURE
- STRESS ~ ,
- CONTAMINANT REMOVAL O FI LD EXPERIENCE j - O DETECTION -
l 4
-- - = + , y , - - - .- - - - - - - - -r..,.-,- e-w-,,,w-c.-,%,_ ., -. , . - - --, ,, - - - --,, - --.v = - - -e,w,. m- w- ,,-e,w------e- r.eere-e--
l
. l
~
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SUMMARY
O PRIMARY SIDE CORROSION RATES ARE EXPECTED TO BE MINIMAL AFTER TUBE PLUGGING
- DRY ENVIRONMENT IS LIKELY ;
- TEMPERATURES ARE LOWER IN INACTIVE TUBE
- LACK OF HYDROGEN, IF TUBE IS WET, WILL RESULT IN VERY LOW CORROSION RATE.
O SECONDARY SIDE CORROSION MAY CONTINUE AFTER TUBE PLUGGING IN SOME CASES BUT THE CORROSION RATE WILL BE SIGNIFICANTLY REDUCED.
- LOWER TEMPER TURE OF PLUGGED TUBE LACK OF HEAT FLUX WILL PRECLUDE FURTHER CONCENTRATION OF CONTAMINANTS REMOVAL OF RESIDUAL CONTAMINANTS TO THE BULK ENVIRONMENT WILL OCCUR AT A RATE DEPENDENT UPON LOCAL GEOMETRY AND HYDRAULIC CONDITIONS.
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SUMMARY
(cont) i . .
O CONTAMINANT REMOVAL AND CORROSION INHIBITION ACTIONS MAY RESULT IN CESSATION OF CORROSION.
. OPTIONS:
~ SLUDGE LANCING CREVICE FLUSHING / BUNDLE FLUSH CHEMICAL CLEANING
- BORIC ACID APPLICATION
- ELIMINATION OF CONTAMINANT INGRESS O OPERATIONALLY INDUCED STRESSES ARE SIGNIFICANTLY LOWER IN A PLUGGED VERSUS AN ACTIVE TUBE. HOOP STRESS IS REDUCED TO A GRESTER EXTENT THAN AXIAL STRESSES.
1 O SEPARATION OF INCONEL 600 TUBING IS NOT KNOWN TO OCCUR IN PLUGGED TUBES BASED ON FIELD AND LABORATORY KNOWLEDGE.
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" INTACT TUBE i
AN INTACT TUBE IS ANY TUBE THAT DOES NOT CONTAIN DEFECTS WHICH WOULD RESULT IN ITS INABILITY TO RESIST THE LOAD IMPOSED BY A SEPARATED TUBE. THE STRUCTURAL LIMIT IS MET BY ANY TUBE WITH A 3600 CIRCUMFERENTI AL INDICATION WITH LESS THAN 92 F'ERCENT WALL PE OF OR BY AN AREA OF WALL REMAINING EQUAL TO OR GREATER THAN 135
. NOMINAL WALL THICKNESS (WHICH CORRESPONDS TO A REMAIAING CROSSECTIONAL AREA OF O.034 IN 2 ),
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- j INTACT TlBE DElailNATION S
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- DOES LOAD OF DISPLACED DOES TIEE CONTAIN IS INDICATION
!, DOES TIEE CONTAIN 7 92% TLBE EXCEED TE SIRtCJ AL
!j ANY INDICATIONSt ANY CIRCLNFERENTIAL LIMIT g (0.03I4 IND i{ \ INDICATIONSg THRU-WALL l w
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v I YES' .
V C YES .
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. NON-
. TUBE i -
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NO NO I NO NO v V
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INTACT TIEE
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