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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212H2031999-09-27027 September 1999 Forwards Operator Licensing Exams Administered at Monticello Nuclear Generating Plant During Wk of 990823.Encl Consists of Facility Submitted Outline & Initial Exam Submittal ML20216G4221999-09-27027 September 1999 Forwards NRC Operator Licensing Exam Rept 50-263/99-301 (Including Completed & Graded Tests) for Tests Administered During Wk of 990823 at Monticello Nuclear Generating Plant ML20212F5461999-09-23023 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 ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20202H6671999-02-0101 February 1999 Notification of 990223 Meeting with Util in Rockville,Md to Discuss Need for TR on Util Analytical Methods Used for Other NRC Licensees,Epri Schedule for Completion of CPM3/ Coretran Analysis Topical & Util Transition Plan ML20202H6321999-02-0101 February 1999 Notification of 990224 Meeting with Util in Rockville,Md to Discuss Implications of Util Recently Extended Commitment for Plant ITS Submittal,Nrc Initiative Toward risk-informed TSs & Interfacing ITS Conversion with Other Activities ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20206S6521998-08-18018 August 1998 Informs That During 980708-10 ACRS 454th Meeting,Several Matters Were Discussed & Listed Repts & Letters Completed. Executive Director Also Authorized to Transmit Noted Memos ML20236U7851998-07-24024 July 1998 Informs That During 453rd & 454th Meetings of ACRS on 980603-05 & 0708-10,NRC Reviewed GE Nuclear Energy Program Associated W/Extended Power Uprates for Operating BWRs & Application for NSP for Power Level Increase for MNGP NUREG-1635, Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr1998-07-0707 July 1998 Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr ML20249A8041998-06-15015 June 1998 Notification of 980630 Meeting W/Util in Rockville,Md to Discuss Issues Related to Conversion to Improved Std TSs for Monticello Nuclear Generating Plant ML20248D7081998-05-26026 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend Supporting Monticello Power Uprate Program ML20216C3931998-05-11011 May 1998 Notification of 980521 Meeting W/Northern States Power Co & GE in Rockville,Md to Discuss Status of Staff Review of Proposed Power Uprate Program for Plant ML20217F2561998-03-20020 March 1998 Notification of 980330 Meeting W/Util to Discuss Licensee Response to Staff Request for Addl Info on Licensee Uprate Program.Meeting Will Be Held in Rockville,Md ML20198Q1881998-01-13013 January 1998 Forwards Nonproprietary Version of Montecello & Cooper Trip Rept to PDR ML20198N0251998-01-12012 January 1998 Discusses 971215-16 NRR Audit of Monticello Strainer Test. Tests Were Established to Develop Data for Strainer Design Installed in NPP ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20216F9711997-09-0505 September 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Current Issues Re Environ Qualification of Equipment at Plant ML20210T1371997-09-0303 September 1997 Notification of 970910 Meeting W/Ge & Southern Co in Rockville,Md to Discuss Status of Boiling Water Reactor Power Uprate Program 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 ML20129B6031996-10-18018 October 1996 Notification of 961105 Meeting W/Util in Rockville,Md to Discuss Contents of NSP License Amend Request Supporting Plant Power Upgrade Program NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20059H5891994-01-24024 January 1994 Notification of 940202 Meeting W/Util in Rockville,Md to Discuss Plans for Implementation of Rwl Mod as Required by NRC Bulletin 93-003 ML20057B4721993-09-15015 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Installation of Water Level Monitoring Instrumentation at Plant ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20127K6681992-11-20020 November 1992 Undated Memo Discussing Status of Field Erected Reactor Vessel Fabrication Review ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref 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 ML20211N7961987-02-19019 February 1987 Requests Consideration of Encl Util 861223 Request That 860228 Application for Extension of Duration of Licenses DPR-57 & NPF-5 Be Given Higher Review Priority.Util Requests Completion of Review by 870331 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20210T3791986-10-0202 October 1986 Notification of 861017 Meeting W/Utils in Bethesda,Md to Discuss Issues Affecting Operating Reactors & NRC ML20211N8311986-10-0101 October 1986 Proposes Listed Schedule for Completion of Reviews of OLs Extensions for Listed Facilities Based on Low Priority of Effort.Plant Sys Branch Will Coordinate Responses & Recipients Will Be Provided W/Integrated Plant SERs ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20211E5131986-06-0606 June 1986 Discusses Inputs for SALP 6 Assessment for Dec 1984 - Mar 1986,due on 860618.Inputs Should Be Typed on 5520 Sys & Remain on Sys Until SALP Board Meeting Held.Listing of Insps Conducted During Assessment Period Encl ML20155F1941986-04-10010 April 1986 Summarizes Operating Reactor Events Meeting 86-11 on 860407 Re Events Since 860331.List of Attendees,Discussion of Events,Status of Assignments & Assigned Completion Dates for Items Encl.Response Requested for Incomplete Assignments ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20198G2001985-11-0505 November 1985 Recommends Issuance of IE Info Notice Re Possible LOCA at High/Low Pressure Interface After Fire Damage Occurs in Control Room.Problem Discovered During Fire Protection re-review ML20087A8311984-03-0505 March 1984 Forwards Monticello Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Evaluation & Monticello Nuclear Power Plant Full-Scale Joint Emergency Exercise on 830223, Final Rept ML20207L3491983-11-30030 November 1983 Advises That Scheme Described in Licensee 830929 Request for Extension of Date for Complying w/10CFR50.54 Unsatisfactory. Mods May Result in Shift Supervisor Spending Less Time in Control room.Davis-Besse Proposal Also Unacceptable ML20058G6051982-07-13013 July 1982 Forwards Draft Ltr Clarifying Confusion During LANL 820706-09 Site Visit to Collect Data for Vital Area Analysis Program.Concerns Re Releasing of Data Resolved.Future Visits Will Be Endowed W/Official Imprimatur ML20148F1051978-10-24024 October 1978 Forwards Memos Re Recent Problems in Pipe Support Base Plate design.(ANO:7811020332,7811020336, & 7811020343.) ML20148G2271978-10-24024 October 1978 Forwards 780929 Memo Re Results of Recent Fire Protec Res Test Conducted at Underwriters Lab. (See ANO: 7810050359, 7810050373.) ML20125A4051978-09-0101 September 1978 Responds to Bajwa 780831 Request for Review of Nonradiological Ets.Several Critical Inconsistencies Still Exist Between Fes Findings & ETS 1999-09-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212H2031999-09-27027 September 1999 Forwards Operator Licensing Exams Administered at Monticello Nuclear Generating Plant During Wk of 990823.Encl Consists of Facility Submitted Outline & Initial Exam Submittal ML20216G4221999-09-27027 September 1999 Forwards NRC Operator Licensing Exam Rept 50-263/99-301 (Including Completed & Graded Tests) for Tests Administered During Wk of 990823 at Monticello Nuclear Generating Plant ML20212F5461999-09-23023 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 ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20202H6321999-02-0101 February 1999 Notification of 990224 Meeting with Util in Rockville,Md to Discuss Implications of Util Recently Extended Commitment for Plant ITS Submittal,Nrc Initiative Toward risk-informed TSs & Interfacing ITS Conversion with Other Activities ML20202H6671999-02-0101 February 1999 Notification of 990223 Meeting with Util in Rockville,Md to Discuss Need for TR on Util Analytical Methods Used for Other NRC Licensees,Epri Schedule for Completion of CPM3/ Coretran Analysis Topical & Util Transition Plan ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20206S6521998-08-18018 August 1998 Informs That During 980708-10 ACRS 454th Meeting,Several Matters Were Discussed & Listed Repts & Letters Completed. Executive Director Also Authorized to Transmit Noted Memos ML20236U7851998-07-24024 July 1998 Informs That During 453rd & 454th Meetings of ACRS on 980603-05 & 0708-10,NRC Reviewed GE Nuclear Energy Program Associated W/Extended Power Uprates for Operating BWRs & Application for NSP for Power Level Increase for MNGP NUREG-1635, Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr1998-07-0707 July 1998 Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr ML20249A8041998-06-15015 June 1998 Notification of 980630 Meeting W/Util in Rockville,Md to Discuss Issues Related to Conversion to Improved Std TSs for Monticello Nuclear Generating Plant ML20248D7081998-05-26026 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend Supporting Monticello Power Uprate Program ML20216C3931998-05-11011 May 1998 Notification of 980521 Meeting W/Northern States Power Co & GE in Rockville,Md to Discuss Status of Staff Review of Proposed Power Uprate Program for Plant ML20217F2561998-03-20020 March 1998 Notification of 980330 Meeting W/Util to Discuss Licensee Response to Staff Request for Addl Info on Licensee Uprate Program.Meeting Will Be Held in Rockville,Md ML20198Q1881998-01-13013 January 1998 Forwards Nonproprietary Version of Montecello & Cooper Trip Rept to PDR ML20198N0251998-01-12012 January 1998 Discusses 971215-16 NRR Audit of Monticello Strainer Test. Tests Were Established to Develop Data for Strainer Design Installed in NPP ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20216F9711997-09-0505 September 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Current Issues Re Environ Qualification of Equipment at Plant ML20210T1371997-09-0303 September 1997 Notification of 970910 Meeting W/Ge & Southern Co in Rockville,Md to Discuss Status of Boiling Water Reactor Power Uprate Program 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 ML20129B6031996-10-18018 October 1996 Notification of 961105 Meeting W/Util in Rockville,Md to Discuss Contents of NSP License Amend Request Supporting Plant Power Upgrade Program NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20059H5891994-01-24024 January 1994 Notification of 940202 Meeting W/Util in Rockville,Md to Discuss Plans for Implementation of Rwl Mod as Required by NRC Bulletin 93-003 ML20057B4721993-09-15015 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Installation of Water Level Monitoring Instrumentation at Plant ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20127K6681992-11-20020 November 1992 Undated Memo Discussing Status of Field Erected Reactor Vessel Fabrication Review ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref 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 ML20215L3101987-05-0707 May 1987 Staff Requirements Memo Re Commission 870430 Affirmation/ Discussion & Vote in Washington,Dc on SECY-87-68A Concerning Order to Rescind 861020 Order Directing Licensee to Show Why OL Should Not Be Modified.Order Signed on 870501 ML20211N7961987-02-19019 February 1987 Requests Consideration of Encl Util 861223 Request That 860228 Application for Extension of Duration of Licenses DPR-57 & NPF-5 Be Given Higher Review Priority.Util Requests Completion of Review by 870331 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20210T3791986-10-0202 October 1986 Notification of 861017 Meeting W/Utils in Bethesda,Md to Discuss Issues Affecting Operating Reactors & NRC ML20211N8311986-10-0101 October 1986 Proposes Listed Schedule for Completion of Reviews of OLs Extensions for Listed Facilities Based on Low Priority of Effort.Plant Sys Branch Will Coordinate Responses & Recipients Will Be Provided W/Integrated Plant SERs ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20211E5131986-06-0606 June 1986 Discusses Inputs for SALP 6 Assessment for Dec 1984 - Mar 1986,due on 860618.Inputs Should Be Typed on 5520 Sys & Remain on Sys Until SALP Board Meeting Held.Listing of Insps Conducted During Assessment Period Encl ML20155F1941986-04-10010 April 1986 Summarizes Operating Reactor Events Meeting 86-11 on 860407 Re Events Since 860331.List of Attendees,Discussion of Events,Status of Assignments & Assigned Completion Dates for Items Encl.Response Requested for Incomplete Assignments ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20198G2001985-11-0505 November 1985 Recommends Issuance of IE Info Notice Re Possible LOCA at High/Low Pressure Interface After Fire Damage Occurs in Control Room.Problem Discovered During Fire Protection re-review ML20087A8311984-03-0505 March 1984 Forwards Monticello Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Evaluation & Monticello Nuclear Power Plant Full-Scale Joint Emergency Exercise on 830223, Final Rept ML20207L3491983-11-30030 November 1983 Advises That Scheme Described in Licensee 830929 Request for Extension of Date for Complying w/10CFR50.54 Unsatisfactory. Mods May Result in Shift Supervisor Spending Less Time in Control room.Davis-Besse Proposal Also Unacceptable ML20058G6051982-07-13013 July 1982 Forwards Draft Ltr Clarifying Confusion During LANL 820706-09 Site Visit to Collect Data for Vital Area Analysis Program.Concerns Re Releasing of Data Resolved.Future Visits Will Be Endowed W/Official Imprimatur ML20148F1051978-10-24024 October 1978 Forwards Memos Re Recent Problems in Pipe Support Base Plate design.(ANO:7811020332,7811020336, & 7811020343.) ML20148G2271978-10-24024 October 1978 Forwards 780929 Memo Re Results of Recent Fire Protec Res Test Conducted at Underwriters Lab. (See ANO: 7810050359, 7810050373.) 1999-09-27
[Table view] |
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"'4 UNITED STATES
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REGION 111 799 ROOsCVELT ROAD
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'n O- GLEN ELLYN. ILLINOIS 60137 July 10, 1968 J. P. O'Reilly,. Chief, Reactor Inspection and Enforcement Branch Division of Compliance, Headquartero COMPLIANCE INQUIRY EMORANDUM NORTHERN STATES POWER (MONTICELLO)
DOCKET NO. 50-263 STUB TUBE MATERIAL INCLUSIONS AT MONTICELLO During a visit to the subject facility on June 27, Messrs. Jones, Reinmuth, Lofy, and Feierabend were informed by Northern States Power (NSP) personnel that Chicago Bridge and Iron (CB&I) had discovered small inclusions in.the Inconel tubing from which the reactor pressure vessel stub tubes were being fabricated. The inspectors were informed that CB&I and their consultant had performed a series of metallurgical investigations which proved that the material 1: question was acceptable for the intended service. General Electric personnel at the site ag reported to have stated that the material met the code and was 4cceptable in their opinion.
On July 3,1968, Messrs. Thornburg, Jones, and Feierabend visited the CB&I corporate offices in Oak Brook, Illinois, to discuss the matter with their management. Discussions were conducted with:
Mr. Perry Arnold, Vice President, Welding Mr. Ed Varnum, Manager, Quality Control Mr. Oscar Seth, Metallurgist The following information was obtained:
A. Material Specifications The. material in question was produced by the Huntington Alloy Products Division of the International Nickel Company (INCO). The material-is designated as Inconel 600 tubing with an ID of 6" and a vall thickness ofes1". The certified mill analyses for two heats of the material as compared to ASTM specifications are shown in Table I below:
u 9212040469 680724 PDR ADOCK 0S000263 S PDR f
., .4 J. P. O'Reilly July 10 1968 TABLE I 7.C Mn Fe S Si Cu Ni Cr Specification 0.10 1.0 6.10 0.015 0.5 0.5 72 _
Aa.17 Heat No. 6400 0.09 0.19 7.15 0 . 00 .' O.23 0.24 76.80 15.27 Heat No. 6569 0.02 0.13 8.15 0.007 0.20 0.21 76.96 14.27 The material certification report reviewed by the inspectors' contained the following statement:
"Af ter proper surface preparation the naterial will be capable of meeting the applicable ultrasonic and liquid penetrant requirements of Section III Article 3 of the boiler code."
B. Action Taken by CB&I Mr. Varnum indicated that the inclusions were-found while the tubing was being machined to the proper OD in the Birmingham Shop of CB&I. The inclusions appeared as minor surface irregularities. They were not detectable by UT or liquid penetrant. A metallurgical investigation was initiated by CB&I, including a visit to INCO by Mr. Varnum. Mr.
Varnum was informed by INCO personnel that such inclusions were normal in Inconel. According to Mr. Varnum they also_ stated that most users of the material bought the material with an extra thickness of --1/4" which is machined off.to eliminate the inclusions.
Dr. Staehle of Ohio State University, an expert in the field of metal corrosion and metallurgy, was retained to study the problem. EHe recommended a metallurgical investigation which included tensile strength-l_
tests, free bend tests, stressed weldment tests, and corrosions tests.
All tests were to be accompanied by photomicrographic studies.
C. Results of Metallurgical Investigations I
( The inspectors reviewed a special report prepared by CB&I which outlined I the investigations performed, the results obtained, and the conclusions reached. The inspectors observed some of the meta:1urgical specimens which resulted from the investigations. The investigatior.s and their results as reported by CB&I are summarized as follows:
- 1. The inclusions are small, approximately 1/32" in length and 2 to 3 mils deep. In general, they are oriented _in the direction of rolling'in strings. In the verst case, five or six inclusions were oriented in a group followed by another group several inches removed. The condit*on varied from several groups per 4 square l
l
[
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J. P. O'Reilly July 10, 1968 inches of surface to a single inclusion per square foot of surface area. The investigations were carried out using the material with the most inclusions (Heat No. 6400). Single inclusions were not joined.
- 2. Battelle Memorial Institute performed a microprobe analysis of the inclusions and reported that they were pure carbon (not a metal carbonitrite).
- 3. ansile strength tests were performed whic' included a number of inclusions in necked area. The test specimens demonstrated tensile properties which significantly exceeded specifications. The samples were taken normal to the direction of rolling, which is the worst case. Photomicrograpns indicated no cracking or failure associated with or originating from the inclusions.
4 Free bend tests were taken to 180 with no failure or cracking observed. The cample specimens were again taken normal to the direc-tion of rolling. Photomicrographs indicated no cracking or failure associated with or originating from the inclusions.
- 5. Laboratory welding tests were performed in highly constrained gec.ne try . A section of 6" ID tubing from Heat No. 6400 was welded to a section of 18" x 18" A-516-Grade 70 plate 2" thick. Photo-micro;raphs of the area of the inconel tubing which "entained the most inclusions indicated no deleterious effects due to welding in highly constrained geometry, viz, no cracks originated from inclusions, etc. No cracks were observed elsewhere in the veld. In the judge-ment of CB&I personnel present, the welding test was performed in more highly constrained geometry than that of the vessel weld.
- 6. A second constrained weld test was performed in a close approxiraa-tion of the geometry of the ,st ainless steci control rod drive housing tube, the Inconel stub tube, and tlse A-516; Grade 70-vessel bottom head. A force of 56,500 pounds was applied normal to the control rod housing tube with a 100 ton jack at the beginning of welding with a reduction to 32,000 pounde during the remainder of the welding cperation. No cracking was observed in the resulting weld-ment. A photomicrograph taken of a section of Inconel tubing in the area of maximum stress showed no deleterious effects.
- 7. A corrosion study was made using an Inconel weldment from Heat No.
6400 in an cicctrolyte containing 200 ppm c1 for 28 days. No cracking was noted.
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J. P. O'Reilly -4. . July 10, 1968
- 8. A corrosion test similar to that described in-item 7 above is now in progress in the CB&I laboratories at a-180 F. The test v111-run for ~<100 days.
- 9. CB&I and their consultant concluded that the inclusions in the material in question did not affect its mechanical properties or its veldability.
D. Observations Made by the Inspectors
- 1. The inclusions.in question extended from two to fou: metal grains in length. In many cases they appeared to be intergranular. The inclusions appeared to be empty _over a considerabb portion of their volume. The carbon may have been removed during the sectioning and polishing process.
- 2. The polished micrographic specimens contained small inclusions which had a pink color which were explained to be titanium carbo-
, nitrides. Most of these very small inclusions, pencil dots at a magnification of x1000, were intergranular.
~
- 3. Mr. Lofy was contacted by the writer. Mr. Lofy stated that he had discussed the matter with Mr. J. ' J. Chyle. The writer also con-tacted Mr. Chyle after returning from CB&I. Mr. Chyle had the following comments on the matter and the licensee's investigation into the problem:
- a. He observed that the licensee't investigation was' proper and responsible,
- b. He observed the carbon does not dissolve and migrate in nicael as it does in iron elloys.
- c. He agreed that the physical properties of the Incon21, including its acidability did not appear to be impaired.
- d. He speculated that the carbon particles may have orig'inated.
from carbon electrodes in an electrical melting process,
- c. " stated that the real question centers around the effect of ac inclusions on the long term performance of the material' 1 le service environment.
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J. P. O'Reilly July 10, 1968 i
E. Region-III position
- 1. We agree that the inclusions apparently have not impaired-the physical properties of the material in question.
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- 2. We believe that CB61 has performed a respousibic investigation of i the properties of the material. We also commend CB&I and NSP on I their efforts to inform Compliance of the problem.
- 3. In the light of experience with stainless steels, we have reserva-tions with regard to the long term performance of the material.in the service envir: ament. This concern could be reduced by the initiation of an in-service material surveillance program. The long term performance of Inconel 600 is unknown at this time.
4 It is perhaps unlikely that the carbonaceous inclusions will result' in a localized region of higher EMF, resulting in a phenomenon similar to intergranular corrosion in stainless steel, but we
, cannot rule out a new mechanism in Inconel or mechanism which takes advantage of the inhomogeneity of the parent material, no matter how slight.
- 5. We recommad that the matter be considered by our specialists and consultants.
- a. -If they agree that the physical properties of the mat'erial are unimpaired by the presence of the inclusions, we should request DRL to require that the applicant carry out a meaningful long term in-service material surveillance ,
program which includes the system material in question.
- b. If they are aware of a possible failure mechanism which the presence of the inclusions might cause in the parent material, other action msy be necessary.
v
.arold D. Thornburg Senior Reactar Inspector f
. . .