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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23
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a b/bb JUN 2 31986 MEMORANDUM FOR: Gary G. Zech, Chief, Vendor Program Branch, Office of Inspection and Enforcement FROM: Charles E. Norelius, Director, Division of Reactor Projects, Region III
SUBJECT:
VENDOR FAILURE TO COMPLY WITH QUALITY ASSURANCE PROGRAM REQUIREMENTS Region III received a letter from Wisconsin Electric Power Company concerning the failure of BIVC0 Valve Company, a division of Titeflex Corporation, to comply with Quality Assurance program requirements when supplying check valves for use in the containment sampling system at Point Beach Units 1 and 2.
Additional information is contained in the letter which is included as Attachment 1. This issue is forwarded to you as a matter under your cognizance with a request for followup inspection.
Should you have any questions, please contact I. N. Jackiw of my staff at (FTS) 388-5697.
" original Signed by C.f. Norpffus#
Charles E. Norelius, Director Division of Reactor Projects Region III cc w/ attachment:
C. E. Norelius W. G. Guldemond I. N. Jackiw M. J. Farber hbk62gDg g gg 6 S
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p c ,l Nsconsm Electnc mcwem 231 w MICHICAN P O BOX 2046 MILWAUKEE. wt 53701 VPNPD- 8 6- 18 5 NRC-85-34 May 8, 1986 Mr. J. G. Keppler, Regional Administrator Of fice of Inspection and Enforcement, Region III U. S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
DOCKET NOS. 50-266 AND 50-301 VENDOR FAILURE TO COMPLY WITH QA PROGRAM REQUIREMENTS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 This letter is to inform you of a nonconformance discovered at the Point Beach Nuclear Plant concerning the procurement of check valves for use in the containment sampling system at Point Beach Units 1 and 2. These check valves were purchased from BIVCO Valve Company, a Division of Titeflex Corporation, located at 603 Hendee Road in Springfield, Massachusetts.
In 1983 four check valves, identified by model number 1016555V-0.5S, were ordered under Wisconsin Electric Purchase Order No. B44001-P from BIVCO. The purchase order specified that the subject l valves were to be manufactured and inspected in accordance with the Titeflex quality assurance program which had been reviewed and accepted by Wisconsin Electric. At the time of our receipt of the valves, the vendor provided certification that these !
l valves had been manufactured in accordance with these requirements. l During the installation and testing of the modifications to the containment sampling system, some leakage problems were experienced with these valves. We subsequently modified the system design to provide manual isolation valves in series with the vendor's check l valves and had several of the valves reworked by the vendor and returned to Point Beach.
f'?M4
Mr. J . G. Esppler JNav B, 1986 Page 2 As a result of a January 26, 1986 audit of this vendor conducted by Wisconsin Electric Quality Assurance personnel, we determined that the subject check valves had been manuf actured and supplied essentially as of f-the-shelf or commercial grade items. We f urther determined that , contrary to the certification received, the specified QA program had not been implemented.
This nonconformance was evaluated in accordance with Wisconsin Electric Quality Assurance procedures and reviewed by our Nuclear Engineering Safety Review Committee for potential 10 CFR 21 reportability. The vendor was informed of our findings at the post-audit meeting and had already issued a Corrective Action Request and Report in accordance with their internal procedures.
Our evaluation determir.ed that a f ailure of these check valves to maintain leak tightness would not result in creation of a substantial safety hazard. The structural integrity of the valve body boundary is verified during each refueling outage by means of a leak check of the containment sampling system. This is a low pressure system, nominally 5 psig, which is isolated from the containment until containment pressure is less than 5 psig. Because of these particular design, testing, and operating circumstances, we have concluded that this non-conformance is not strictly reportable under the requirements of 10 CFR 21.
As a result of this nonconformance, the vendor has been removed from our list of qualified suppliers. We have also discussed this matter with vendor personnel. They have stated that no other valves have been supplied to the nuclear industry under these circumsta nces . We notified them that we would, nonetheless, inform the NRC of our findings.
Very truly yours, Y
(,'l G/ O C.W. Fay Vice President Nuclear Power Copies to NRC Resident Inspector NRC Office of Inspection and Enforcement, Washington, D. C.
J. G. Makis, Vice President & General Manager, Ti'eflex Corporation J. M. Lalikos, Vice President Engineering, Titeflex Corporation W. Vernon, General Manager, BIVCO Valve Company
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