|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML18152A2161999-02-23023 February 1999 Summary of 990119 Meeting with Util to Discuss Issues Re GL 97-04, Assurance of Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps ML18153B1971994-12-27027 December 1994 Notification of 950110 Meeting W/Util in Rockville,Md to Discuss Vision 2000 Program Update,Current & Future Licensing Activities & Cost Beneficial Licensing Actions ML18151A3451994-06-0303 June 1994 Summary of 940216 Meeting W/Vepco Re VEPCO Proposal for Five Year Term License Renewal,For Surry Npgs,Units 1 & 2 & North Anna Npgs,Units 1 & 2.List of Attendees,Agenda & Other Handouts Encl ML20059H8251993-10-29029 October 1993 Summary of 931028 Meeting W/Util Re Current Licensing Actions Ongoing at Plant.Licensing Actions Discussed Listed ML18152A4531993-09-0808 September 1993 Summary of 930825 Meeting W/Util in Rockville,Md Re Discussions on Integrated Trending Program,Ts Line Item Improvement,Regulatory Requirements Marginal to Safety & Surrey Fire Protection Tss.List of Attendees Encl ML18153D0121992-05-12012 May 1992 Summary of 920330 Meeting W/Util in Rockville,Md Re Significant Licensing Issues for Surry Units 1 & 2 & North Anna Units 1 & 2 ML18153C6941991-08-0808 August 1991 Summary of 910801 Meeting W/Util in Rockville,Md to Provide Opportunity to Describe Efforts Underway to Enhance Inservice Testing Program for Pumps & Valves at Both Surry & North Anna Stations ML18153C5891991-03-29029 March 1991 Summary of 910227 Meeting W/Util in Rockville,Md Re General Overall Status & Direction of Plants & Programs,Including Nuclear & Industrial Safety,Human Resources,Regulatory Compliance & Performance & Cost Mgt ML18153C2451990-06-0505 June 1990 Summary of 900523 Meeting W/Util in Rockville,Md Re Recent Changes in Matls Procurement Program.List of Attendees & Viewgraphs Encl ML20248D8821989-09-26026 September 1989 Summary of 890907 Meeting W/Util in Rockville,Md to Discuss Safety Sys Outage Mods Insp Finding IC-3,alleging That non-Class 1E Pressure Transmitters Powered from Class 1E Buses W/O Proper Isolation.Viewgraphs & Attendees List Encl ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML18153B7971989-07-0606 July 1989 Summary of 890612 Meeting W/Util in Rockville,Md Re Plant Configuration Mgt Program.Informs That Goal of Program Is to Confirm That as-built Plants in Conformance W/Licensing Design Basis as Described in FSAR ML20246B8971989-07-0505 July 1989 Summary of 890615 Meeting W/Util & Westinghouse Re Lead Plant Implementation for Westinghouse Merits Tech Specs. List of Attendees,Agenda & Merits Program Description Encl 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 ML18153B7071989-05-0404 May 1989 Summary of 890419 Meeting W/Util in Rockville,Md Re Followup on NRC Bulletin 80-11, Masonry Wall Design. NRC Requested Documentation of as-built Boundary Conditions, Available Conservatisms & Field Verifications ML18153B6791989-04-11011 April 1989 Summary of 890330 Meeting W/Util in Rockville,Md Re Util Overall long-term Improvement Plan to Enhance Plant Operations ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20154P4171988-05-13013 May 1988 Summary of 880408 Meeting W/Util & Arrowhead Industrial Water,Inc in Rockville,Md Re Very Low Level Radioactive Concentrations Observed in Reverse Osmosis Sys Used to Generate Makeup Water at Plant.Attendance List Encl ML20151L0681988-04-0404 April 1988 Summary of 880127 CRGR Meeting 128 Re Listed Items,Including Review of Proposed Generic Ltr to Inform Licensees of New NRC Position on Guidelines for Determining Whether Operating Basis Earthquake Limits Exceeded ML20148K0921988-01-22022 January 1988 Summary of ACRS Subcommittee on Metal Components & Thermal Hydraulic Phenomena 871215 Meeting W/Vepco & Westinghouse in Washington,Dc Re Steam Generator Tube Rupture Failure & Dl Johnson Comments on Criteria for ECCS Rule 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 ML20238A5321987-08-26026 August 1987 Summary of 870729 Meeting W/Util & Westinghouse at Plant Re 870715 Steam Generator Tube Rupture.List of Attendees, Meeting Viewgraphs & North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept Encl ML20237G3791987-08-11011 August 1987 Summary of Operating Reactors Events Meeting 87-23 on 870721.List of Attendees,Viewgraphs & Summary of Reactor Scrams & Significant Events Encl ML18149A3681986-10-0909 October 1986 Summary of 860902 Meeting W/Util in Bethesda,Md Re Security Plans.Interpretation of Detection as Used in Regulations Addressed.Viewgraphs Encl ML20149C1001986-06-20020 June 1986 Discusses Attendance at 860528 & 29 INPO Accreditation Board Meetings.Board Attendees Listed & Major facility-specific Issues & Util Responses Discussed.Evaluation Method Appears Effective Overall.Nrc Involvement Should Be Maintained ML20141F4091986-04-10010 April 1986 Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20151N3021985-12-19019 December 1985 Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl ML20141E9501985-11-18018 November 1985 Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl ML20136C5141985-11-11011 November 1985 Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl ML20149B8651985-11-0404 November 1985 Summary of INPO Accreditation Board 851023-24 Meetings in Atlanta,Ga Re Training Programs for Listed Facilities, Performance Indicators,Nrc Exam Failure Rate & Instructor Qualifications ML20133E4631985-10-0101 October 1985 Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl ML20138A1201985-09-23023 September 1985 Trip Rept of 850617-20 Site Visits Re Reduction of Wrong Unit/Wrong Train Events at Facilities ML20133Q4171985-09-0505 September 1985 Summary of 850823 Meeting W/Util in Atlanta,Ga Re Development of Scaling Factors for 10CFR61.55 Compliance. Attendance List Encl ML20128C9601985-06-25025 June 1985 Summary of 850607 Meeting W/Util in Bethesda,Md Re Svc Water Sys Piping Corrosion & Preservation Program.Nrr Approval Given to Portion of Util Mechanical Cleaning Program ML20127A7001985-06-0505 June 1985 Summary of 850506 Meeting W/Utils & Bechtel Corp in Bethesda,Md Re Respiratory Protection for Subatmospheric Containments.Agenda & List of Attendees Encl ML20024D4061983-07-25025 July 1983 Trip Rept of 830714 Site Visit for NRC & Lll to Obtain Addl Info Re Recurring Main Transformer Failures ML18139B9671982-07-13013 July 1982 Trip Rept of 820512-14 Visit to Facilities Re Radiological Effluent Tech Specs ML18139B6491981-12-0202 December 1981 Summary of 811113 Meeting W/Util in Richmond,Va Re Emergency Operations Facility & Technical Support Ctr.Agenda,Attendee List & Viewgraphs Encl ML20032C9041981-10-21021 October 1981 Trip Rept of 811008 Site Visit & Concurrent IE Plant Insp to Discuss Technical Assignment Control Sys for Facilities. Areas Inspected:Const of Machine Shop Bldg,Auxiliary Feedwater Pumps & Mods Underway on Powdex Demineralizers ML20031F1401981-10-0101 October 1981 Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl ML20065H6621981-08-10010 August 1981 Summary of 810806 Operating Reactor Events Meeting.Related Info Encl.Next Meeting Scheduled for 820812 ML20030A9071981-07-22022 July 1981 Trip Rept of 810709 Site Visit to Observe Effects of Main Phase B Transformer Fire Which Occurred on 810703 ML20010D6101981-06-24024 June 1981 Minutes of ACRS Ad Hoc Subcommittee on Decay Heat Removal Sys 810505 Meeting Re Response to Commissioner Gilinsky Questions on RHS & Low Power Injection Sys Improvements & Re NRC Sponsored Work at Sandia Alternate Heat Removal Sys ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20126H6141981-04-0909 April 1981 Summary of 810320 Meeting W/Utils,Westinghouse & EPRI in Bethesda,Md Re Testing of Block Valves.Attendance List, Handouts & Vendor Ltrs Encl 1999-02-23
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML18152A2161999-02-23023 February 1999 Summary of 990119 Meeting with Util to Discuss Issues Re GL 97-04, Assurance of Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps ML18153B1971994-12-27027 December 1994 Notification of 950110 Meeting W/Util in Rockville,Md to Discuss Vision 2000 Program Update,Current & Future Licensing Activities & Cost Beneficial Licensing Actions ML18151A3451994-06-0303 June 1994 Summary of 940216 Meeting W/Vepco Re VEPCO Proposal for Five Year Term License Renewal,For Surry Npgs,Units 1 & 2 & North Anna Npgs,Units 1 & 2.List of Attendees,Agenda & Other Handouts Encl ML20059H8251993-10-29029 October 1993 Summary of 931028 Meeting W/Util Re Current Licensing Actions Ongoing at Plant.Licensing Actions Discussed Listed ML18152A4531993-09-0808 September 1993 Summary of 930825 Meeting W/Util in Rockville,Md Re Discussions on Integrated Trending Program,Ts Line Item Improvement,Regulatory Requirements Marginal to Safety & Surrey Fire Protection Tss.List of Attendees Encl ML18153D0121992-05-12012 May 1992 Summary of 920330 Meeting W/Util in Rockville,Md Re Significant Licensing Issues for Surry Units 1 & 2 & North Anna Units 1 & 2 ML18153C6941991-08-0808 August 1991 Summary of 910801 Meeting W/Util in Rockville,Md to Provide Opportunity to Describe Efforts Underway to Enhance Inservice Testing Program for Pumps & Valves at Both Surry & North Anna Stations ML18153C5891991-03-29029 March 1991 Summary of 910227 Meeting W/Util in Rockville,Md Re General Overall Status & Direction of Plants & Programs,Including Nuclear & Industrial Safety,Human Resources,Regulatory Compliance & Performance & Cost Mgt ML18153C2451990-06-0505 June 1990 Summary of 900523 Meeting W/Util in Rockville,Md Re Recent Changes in Matls Procurement Program.List of Attendees & Viewgraphs Encl ML20248D8821989-09-26026 September 1989 Summary of 890907 Meeting W/Util in Rockville,Md to Discuss Safety Sys Outage Mods Insp Finding IC-3,alleging That non-Class 1E Pressure Transmitters Powered from Class 1E Buses W/O Proper Isolation.Viewgraphs & Attendees List Encl ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML18153B7971989-07-0606 July 1989 Summary of 890612 Meeting W/Util in Rockville,Md Re Plant Configuration Mgt Program.Informs That Goal of Program Is to Confirm That as-built Plants in Conformance W/Licensing Design Basis as Described in FSAR ML20246B8971989-07-0505 July 1989 Summary of 890615 Meeting W/Util & Westinghouse Re Lead Plant Implementation for Westinghouse Merits Tech Specs. List of Attendees,Agenda & Merits Program Description Encl 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 ML18153B7071989-05-0404 May 1989 Summary of 890419 Meeting W/Util in Rockville,Md Re Followup on NRC Bulletin 80-11, Masonry Wall Design. NRC Requested Documentation of as-built Boundary Conditions, Available Conservatisms & Field Verifications ML18153B6791989-04-11011 April 1989 Summary of 890330 Meeting W/Util in Rockville,Md Re Util Overall long-term Improvement Plan to Enhance Plant Operations ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20154P4171988-05-13013 May 1988 Summary of 880408 Meeting W/Util & Arrowhead Industrial Water,Inc in Rockville,Md Re Very Low Level Radioactive Concentrations Observed in Reverse Osmosis Sys Used to Generate Makeup Water at Plant.Attendance List Encl ML20151L0681988-04-0404 April 1988 Summary of 880127 CRGR Meeting 128 Re Listed Items,Including Review of Proposed Generic Ltr to Inform Licensees of New NRC Position on Guidelines for Determining Whether Operating Basis Earthquake Limits Exceeded ML20148K0921988-01-22022 January 1988 Summary of ACRS Subcommittee on Metal Components & Thermal Hydraulic Phenomena 871215 Meeting W/Vepco & Westinghouse in Washington,Dc Re Steam Generator Tube Rupture Failure & Dl Johnson Comments on Criteria for ECCS Rule 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 ML20238A5321987-08-26026 August 1987 Summary of 870729 Meeting W/Util & Westinghouse at Plant Re 870715 Steam Generator Tube Rupture.List of Attendees, Meeting Viewgraphs & North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept Encl ML20237G3791987-08-11011 August 1987 Summary of Operating Reactors Events Meeting 87-23 on 870721.List of Attendees,Viewgraphs & Summary of Reactor Scrams & Significant Events Encl ML18149A3681986-10-0909 October 1986 Summary of 860902 Meeting W/Util in Bethesda,Md Re Security Plans.Interpretation of Detection as Used in Regulations Addressed.Viewgraphs Encl ML20149C1001986-06-20020 June 1986 Discusses Attendance at 860528 & 29 INPO Accreditation Board Meetings.Board Attendees Listed & Major facility-specific Issues & Util Responses Discussed.Evaluation Method Appears Effective Overall.Nrc Involvement Should Be Maintained ML20141F4091986-04-10010 April 1986 Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20151N3021985-12-19019 December 1985 Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl ML20141E9501985-11-18018 November 1985 Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda Encl ML20136C5141985-11-11011 November 1985 Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl ML20149B8651985-11-0404 November 1985 Summary of INPO Accreditation Board 851023-24 Meetings in Atlanta,Ga Re Training Programs for Listed Facilities, Performance Indicators,Nrc Exam Failure Rate & Instructor Qualifications ML20133E4631985-10-0101 October 1985 Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl ML20133Q4171985-09-0505 September 1985 Summary of 850823 Meeting W/Util in Atlanta,Ga Re Development of Scaling Factors for 10CFR61.55 Compliance. Attendance List Encl ML20128C9601985-06-25025 June 1985 Summary of 850607 Meeting W/Util in Bethesda,Md Re Svc Water Sys Piping Corrosion & Preservation Program.Nrr Approval Given to Portion of Util Mechanical Cleaning Program ML20127A7001985-06-0505 June 1985 Summary of 850506 Meeting W/Utils & Bechtel Corp in Bethesda,Md Re Respiratory Protection for Subatmospheric Containments.Agenda & List of Attendees Encl ML18139B6491981-12-0202 December 1981 Summary of 811113 Meeting W/Util in Richmond,Va Re Emergency Operations Facility & Technical Support Ctr.Agenda,Attendee List & Viewgraphs Encl ML20031F1401981-10-0101 October 1981 Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl ML20065H6621981-08-10010 August 1981 Summary of 810806 Operating Reactor Events Meeting.Related Info Encl.Next Meeting Scheduled for 820812 ML20010D6101981-06-24024 June 1981 Minutes of ACRS Ad Hoc Subcommittee on Decay Heat Removal Sys 810505 Meeting Re Response to Commissioner Gilinsky Questions on RHS & Low Power Injection Sys Improvements & Re NRC Sponsored Work at Sandia Alternate Heat Removal Sys ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20126H6141981-04-0909 April 1981 Summary of 810320 Meeting W/Utils,Westinghouse & EPRI in Bethesda,Md Re Testing of Block Valves.Attendance List, Handouts & Vendor Ltrs Encl ML19350A4161981-02-20020 February 1981 Summary of 810218 Meeting W/Anchor/Darling Industries in Bethesda,Md Re Dyna A/Damp Mechanical Snubber & in Place Surveillance Testing.Design of Snubber Meets Inservice Insp Program Requirements.Addl Info May Be Requested ML17328B0601981-02-0303 February 1981 Summary of 810123 Meeting W/Util & Westinghouse Re Low Pressure Turbine Disk Insp.Attendance List & Results of Insp Encl ML19341A9291981-01-12012 January 1981 Summary of 810107 Meeting W/Util in Bethesda,Md Re Leak Testing of RCS Isolation Valves.Tech Spec Page 3/4 4-18 Encl ML19345B9921980-11-21021 November 1980 Summary of ACRS 801106-08 Meeting 247 Re Methods to Strengthen ACRS Role in Regulatory Process,Proposed Changes in Residual Heat Removal Sys of North Anna Unit 2 & Mod & Proposed Operation of Getr ML18139A8891980-11-19019 November 1980 Summary of 801107 Meeting W/Util in Bethesda,Md Re Emergency Plans 1999-02-23
[Table view] |
Text
_ _ _ _ _._
June 25, 1985 Docket Nos. 50-338 and 50-339 MEMORANDUM FOR:
Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing FROM:
Leon B. Engle, Project Manager Operating Reactors Branch No. 3 Division of Licensing
SUBJECT:
SUMMARY
OF MEETING WITH VIRGINIA ELECTRIC AND POWER COMPANY (VEPC0) REGARDING THE NORTH ANNA POWER STATION UNITS N0. 1 AND N0. 2 (NA-1&2) SERVICE WATER SYSTEM PIPIVi CORROSION AND PRESERVATION PROGRAM Introduction A meeting was held on Friday, June 7, 1985 with VEPC0 and the NRC staff in Bethesda, Maryland regarding the subject as noted above. A list of attendees is provided in Enclosure 1.
VEPC0 stated that the North Anna Power Station (NAPS) Service Water Systein (SWS) piping is continuing to experience severe corrosion and pitting. The corrosion rate is approximately 10 mils per year. The corrosion rate is being accelerated due to the aggressive nature of Lake Anna water (pH=6.8) and sulfate reducing bacteria. The corrosion is in the form of general wall thickness reduction and wide spread pitting.
VEPC0's proposed methodology and implementation plan for nechanical cleaning of the SWS was provided in a letter dated February 27, 1985.
Discussion The SWS for the North Anna Power Station is a system that is shared between Units 1 and 2 and consists of two 100% capacity loops with four pumps in each loop. Pump suction is from a reservoir adjacent to Lake Anna and heated water is returned to the reservoir which has a cooling spray array. Makeup for the reservoir is from Lake Anna. The SWS provides cooling to various components and systems that perform a safety function, such as charging pump coolers, seal coolers, and component cooling water heat exchangers. The SWS is, therefore, a safety related system.
6"7 PoM ! M Le P
PDR
. In order to preserve the integrity of the SWS piping, a corrosion inhibitor molybdate-based chemical treatment program was initiated at the service water reservoir in July 1984 Carbon steel test samples exposed to the treated service water 7or intervals up to 60 days have shown a corrosion rate of less than 1 mil per year. However, the treated service water cannot come into contact with the majority of the SWS piping internal surface because of the buildup of corrosion products, silt, and slime which has developed since the units were first licensed for full power operation.
In order for the molybdate-based corrosion inhibitor to be effective, the internal surfaces must be cleaned to bare metal, and until such time that the internal surfaces are cleaned, corrosion will continue to occur beneath the corrosion product buildup in spite of corrosion inhibiting chemicals in the service water.
The internal cleaning method chosen is a mechanical cleaning method known as hydrolasing. Hydrolasing is a process whereby a high pressure (4000 to 8000 psi) water jet is impinged at right angles to the internal surface of the piping. The dislodged corrosion products will be flushed out through openings in the pipe and discharged corrosion products will be collected in temporary collection troughs and settling drums.
VEPC0 stated that the hydrolasing method was chosen because it is a flexible, effective, and the least likely method to remove metal from the piping walls.
Hydrolasing is flexible in that both small and large sections of piping can be ckaied with only minor setup operations.
In addition, the cleaning operations can be scheduled to comply with the NA-1&2 Technical Specification Limiting Conditions of Operation. Access requirements for hydrolasing require only minor modifications such as removing small sections of piping or valves.
NNSoperatingexperienceindicatesthatmanyofthevalvesintheSWSdonot provide tight shutoff. Failure to seat properly is causing problems in isolating equipment for naintenance and Type "C" testing.
,Th'e majority of SUS valves that create isolation problems are flanged or wafer type butterfly valves. The nost probable causes of degradation in SWS valve
' integrity are (1) buildups of corrosion products around valve seating area, (2) corrosion attack of cast iron butterfly valve disc, and (3) valve discs being pulled through their seats thereby causing seat damage.
Therefore, VEPC0 stated that the cleaning operations on the SWS piping will require that all valves in the SWS provide proper isolation. Any valves that do not seat properly will be repaired or replaced.
In many cases, valve repair must be completed before piping can be hydrolased.
The NA SWS is required to operate in all modes of plant operation. The NA-1&?
TS 3/4.7.4 governs the operation of the system during operating Modes 1 through i
4.
Although the TS do not require two loops of the SWS to be operating in Modes 5 and 6, at least one loop must be operable to remove heat from the Residual Heat Removal system and fuel pool. The TS allow for one of the two redundant service water loops to be out of service for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The isolated loop must be placed back in service within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or both units must comence shutting down.
. VEPC0 has prepared detailed work packages during the time that an SWS component or subsystem would be within the TS 72-hour action statement for mechanical cleaning. A detailed schedule has been prepared for each work package covering every activity to be performed during any period of isolction of one of the two redundant SWS loops. A stop-work point is specified to provide adequate time for system closure and pressure testing to ensure the TS action statement for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is not violated. Work will be subdivided into small portions to provide ample margin for completion within the allowable time limit. Eauipment setup will be completed and a thorough check-out of all equipment and tools performed prior to isolating a SWS segment. All personnel performing any portion of the work will be thoroughly briefed prior to commencing start of work. Finally, work will be performed with shifts overlapping to ensure con-tinuity of a detailed work package.
Each work package includes a detailed review in conformance with 10 CFR 50.59 to ensure that the particular work does not create an unreviewed safety question.
In addition, work packages involving isolation of main or branch headers will include an emergency contingency plan. These contingency plans provide in-structions for installing temporary devices such as spool pieces and pipe couplings to insure flow conditions for (1) Loss-of-Coolant Accident, (2) failure of remainino 7perational SWS loop, and (3) flooding through an opened porhion of the syst' a result of valve or operator failure.
Administrs.ve controls to prevent flooding through an opened loop include
" tag-out" procedures which require the notification of the Shift'5unervisor a
and placement of a tag on a component or valve and tagging the cor inent's control room indicators and/or switches.
In addition, valves that'are 18 inches or greater in diameter and are closed to provide main heades isolation will be locked closed.- The locking of these valves is delineated in the detailed work packages.
VEPCO's Plan 4 for completing the mechanical cleaning of the SWS requires six main header isolations and 12 branch header isolations. Ten of the 12 branch header isolations are expected to be approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in duration.
Each period of isolation required to complete pipe cleaning and valve repairs will be separated by a minimum separation of 14 days of normal operation.
By letter dated March 29, 1985, VEPC0 submitted a proposed TS revision which would revise the SWS LCO from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (3 days) to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> (7 days). The safety evaluation supporting the proposed change is based on a probabilistic safety assessment.
If approved by the NRC, VEPC0 would use the SWS 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> LC0 for the mechanical cleaning plan. VEPC0 has committed to revising its submittal by footnoting the appropriate NA-182 TS for the proposed 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> LC0 by stating that the revised LC0 is applicable for the time period applicable for mechanical cleaning and refurbishment of the SWS only.
Conlusions Based on the above, the NRR and Region II staff caucused and informed VEPC0 on their findings. The licensee was informed that NRR finds that portion of VEPCO's mechanical cleaning program for the NA-182 SWS that can be performed under the presently specified NA-182 TS LC0 of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to be acceptable.
,. The cleaning program as documented ir. VEPC0's submittal of February 27, 1985 was not considered an inappropriate use of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LC0 given the current conditions which exist at the plant. This finding for the NA SWS mechanical cleaning program is a plant specific interpretation and does not imply any generic approval for frequent repeated use of LC0's to perform routine maintenance which could be performed during normal plant shutdowns with the appropriate advance planning.
Finally, the staff informed VEPC0 that the March 29, 1985 submittal proposing a 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> LC0 in lieu of the presently stipulated 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LC0 will receive a full review based on a probablistic risk assessment. Until such time as this review is complete, VEPC0 agreed that the use of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LC0 would be limited to the number of time specified in option 4 of their plan described above with a reusable allowance (one or two additional uses of the LCO) for contingencies.
The mechanical cleaning of the major portion of the SWS main leaders will not be perfomed until the staff completes its review of the proposed LC0 for the
{
system. The meeting then adjourned, op;e31sW.edbv Leon B. Engle, Project Manager Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated ORB #3:DL 0
OR zer LEngle:dd EJBut"her 85 6/g/85 6/g5785 i
C MEETING
SUMMARY
DISTRIBUTION Licensee: Virginia Electric and Power Company, (VEPC0) North Anna Unit Nos. 1&2
- Copies also sent to those people on service (cc) list for subject plant (s).
O kk d File i i
- NRC PDR k
L PDR ORBf3 Rdg Project Manager -
f
[Emerg.Preparednessonly)
OELD NSIC i
EJordan, IE PMcKee, IE ACRS-10 JPartlow NRC Meeting
Participants:
E. Butcher M. Branch V. Brownlee M. Virgilio 7
.