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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML19281A8911979-02-0202 February 1979 Summary of 790122-24 Meeting W/Mark I Owners Group in San Jose,Ca Re Validity of Results of Orificing for Scaling. Discussed Lll Tests Showing Loads Derived from 3D Tests Greater than Loads from 2D Tests ML20084P9051970-05-18018 May 1970 Provides Recommendations Re Repair of safe-ends on Reactor Vessel.Recommendations Contingent Upon Type of Failure AEC Wants to Prevent ML20084P9591970-05-0808 May 1970 Forwards Preliminary Rept on Meeting Concerning Nine Mile Point Core Spray Nozzles & Related Piping Sys. Open Areas Listed.W/O Encl ML20084Q6441970-04-0707 April 1970 Comments on Util 700403 Submittal Re Disposition of safe- Ends 1986-06-12
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
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R..W. Stachle 506311avens Corners Road G.dunna, Ohio reply to: Dr. R. W. Staehle The Ohio State Univ.
Dept. of Met. Engr.
116 W. 19th Avenue Columbus, Ohio 43210 18 m y, 1970 t l
Mr. IIarold R. Denton, Chief Tmhnical Support Branch U. S. Atcutic Energy Comtission Division of Canpliance mshington, D. C. 20545 ;
6A
Subject:
Course -of Action on Repairs for Dresden -2 at Nine Mile Point - !
Dear Ibrold:
On May 14 you requested my recammen3ations for a course of action to be taken for the repair of safe ends on the reactor vessels of :
Dresden -2 and Nine Mile Point. The purpose of this letter is to transntit these reammen3ations together with their justification. In addition to these reccanendations I have imluded suggestions for measures to be taken to reduce the likelihood of spurious cracking.
Prinnry RecaumeIxlations The rccarmendations here are contingent upon the kird of " failure" '
which the AEC wishes to avoid:
- 1. For example, if it is desircd to avoid the incideme of any .
transgranular stress corrosion cracking, then it is necessary to replace all stainless steel piping with either a higher nickel alloy, a ferritic stainless steel or a duplex alloy.
In my opinion this is an unroasomble criterion in view of the economic implications. However, it must be kept in mind that incidences of transgranular cracking are always likely in austenitic stainless steel systons ard extrane care must P
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be exerciscd to avoid this phenanenon.
- 2. If it is desired to avoid only the type of cracking cbserved in the first failure of the safe end at Nine Mile Point, then a different course of action is appropriate. It is my operating assumption, ard I think it is the only reacorable one, tlnt the cracking which ms chserved could have lead to a large rupture durim a thornnl transient. Ibwever, it is not appropriate hare to coment on the consequeir;es of the large rupture. Your interpretation of this is much nore expert than mine. It is my contention tint such a failure can result anl that there is a reasomble possibility its initial stages muld not b2 detectcd. Thus, it nny not leak sufficiently for it to be detceted before the major failure occurs.
If the AEC considers that such a failure must be avoided, then I recomterd tlut:
- a. The intergranular made of sensitized TC b2 considered as leading to the extensively penetratcd cracking of the type observal at NG anl IACBPT(.
- b. The MC should require that all safe ends b2 replaced either with solid scctions or wc3d cuerlayed inside ani outside.
- c. The MC should require that a cordition for replacanent is tlut the licensee denonstrate (by test results) the adequacy of the replacanent material ard prccedure through agread upon tests. Incidentally, sane of these tests my be alrcady empleted. These tests should ,
demonstrate (l) that the new nuterial will resist ECC '
in the foua used in the replaccment ard (2) that the configuration usal will not be subject to premature failures as a result of thernnl shock, fatigue, or other appropriate n,cchanical requiranents.
- d. The most reasomble replacanent nuterial is probably Type 303L weld deposited nnterial since this has had wide use as weld overlay nuterial. Acceptable nuterials muld also include Ircoloy-800 ard Inconel-600 providing that other defects are not intrcduccd. The 308L Ins the disadvantage relative to the other tm nuterials of a ready susceptibility to transgranular SCC in chloride environnents. The uncertainties in the latter tm naterials involve their behavior in the weld sensitized cordition with respcct to intergranular ECC in the mter
-Og emironncnts.
I D
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- e. Follo dg i
the repairs the systan mist ) (m be hydrostatically testcd.
l 1 believe t!nt in its re;ulatory capacity the MC las no choice but to rcqaire repair of all cafo ends. The Iuttern of occurrerce of failures contains elenents of frequelcy aid unpredictability which cannot be denicd. Regard] css of the detailed raticialization of the crackirg an1 attorpts by various inrties to obfuscate the issues, tle fact rcnnins that this crackiln is o'curriig with grcnt frequercy (K@ , IACIr.G, Oyster Creek) in sensitizol stainless steel, tlut the crackiny is extensive, airl tlut it was not predictcd. Fran a nuruganent point of view one nust conclude tlnt, regardless of the stress analysis or any other intermaliately amcliorating fixes or calculations, there is a high probability of failures occurring again; further, there is the reasonable prob:tbility that one of the failures nny be the open ended type.
Seconiary Rccom:nesdations There are a rurrber of other reconnen3ations which should be considered at this time. vTnile they are not as .inunliately critical as the prinnry reconnerdations atove, I believe tlnt they should be seriously considerod and chculd fonn the Insis for action taken in the near future.
- 1. Consideration shoald be given to the developnent of improval alloja far :_c:_vice in rc2ctc.r 7= a = =rd pipirg. Th co presently available continue to exhibit problons. Two areas in which I work might be u;rlertaken are the duplex alloys and the high l purity ferritic alloys.
- 2. Consideration should be given to shot peening inside arrl outside surfaces of stainless steel. This would prevent the initiation !
cracking. hhile there are almys questions about coverage of shot peening the probability of SCC is greatly lowered.
- 3. Consideration should be given to an exterior coatirg which would inhibit SCC fran the outside in.
- 4. The criteria for leaks of valves, fittirgs, etc. in operating plants should be reviewed ard tightened. In nrf opinion there sinuld be no drippirn water of any kird anywirre ncnr the reactor or its ccmponents.
4-5.
o o The AFC shouki conluct a }rcxjram to deterntim the offect of crack extent (depth + circtrifercnLial distribation) on the role of n'echnical failure unlec aIprcyrjato loTdirg schwes.
This is a 1resscd to the gaestion: "Ibw aid un:ler wint coalitions would tha fEC crack pwpjate u2 der mcelunical loads c:qteted during service."
- 6. There is a reasomble imentive to determine the extent of the tran; granular !EC on the interml surface observcd by ID7L in exantinity tia interior curface of i ha secon! core spray nnzzle.
CcaTnents anl Justification in Sugxrt of Prinnry Reca'TuoMation
- 1. The first qacation in my niild is wbather the Alr will consider that a canplete Lrcok of any safe eM is sufficiently serious to pose a throat to safcLy. If there is no thrcut, then there is no point in pronulgating any rcqairo'l repair action.
- 2. I believe t]nt thare is a reasomble possibility tlnt the intergranular cracking of the type cbservcd at N@ ard UsCEtR can load to a ecmplete scuerame or substantial yaw n ing of the pipe. Such an assertion is h2scd on the fact tlut in both cases the cracks were penetratcd 50--100? of the wl1 over 1/3 of the circumfereme. Tint such a defect can occur before leaks are fcuM was a great surprise ard also a cause for substantial comern.
J. The critical questions hre relative to tha causative parameters are the lc/cls of oxygen ard stress v.nich are critical. For l example there is the reasonable possibility tlnt the cracking '
may Invc occurred in tJ:e gas pluse where radiolytically rroducal oxygen lnd accumulatul a2d which wuld be naturatcd with water. I Ilosever, for various reasons I believe this to be an unreasonable I assumption. For exanple, the deposition of copper in the IACBVR case suggests tlat vater vns in the crevice for a protracttd period of time. I suggest tlut it is, practically speaking, unreasonable to associate these failures czclusively with these gasifica regions.
With respect to the variable of stress; I believe, along with faith others, that a higher stress nny be requircd to propagate the intergranular cracks than in the case of transgranular cracks.
Ilowever, I l>2lieve it is unreasonable to cut titis effect too fine with respect to dccidizg which safe erd should be repaird. Despite the fact that stress analyses are being coMuctd on as-bailt pipes there is no clear certainty that these analyses are sufficiently necurate with respect to w1nt really cxists.
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- .O o + o j Further, there is no basis for confiderce which suggests that 4
!i these stresses will stay the same during operation. They nuy 1; either imrcase oc decroane. ;
4 A posibly causative Dictcr mr/ be considered th ;<
Despi.te the FIrr by Mrd, T'athis and nrjself s!S,o iryfluoride ion.
the viru]ence !
of this contamimnt in causing SCC of sensitirol netorial, therc {
is no insis for sugqcating tlat it was uniquely caumtive in i the vide range of cases obserwd. It nust be concludul for the I -
present tlnt flueride (as well as chloride) is urdesirable but tJut it is not uniqacly causative for cracking of the haavily sensitizcd nutorial. ...
- 5. There is the additioml issue concerning whether the snaller cracks will propagate later. This nutter is conjcctural.
I?cwever, from the point of viea of public safety it is reasomble to assu.na tlat c<isting cracks will propagate, but at a slcraer i rate. This is the apprcach often usod in the chantical iMustry I when schaSuling the reordering of replaccment nutorials. Naturally, it is toipting to conclude otherwise depending on ones aconantic prejudices or on cne's aversion for politicalinfighting.
There were two instarces at NMP where specimens were taken -
to assess the effects of stress: The flarca region of tha first safe end ard the seccal safe cal. In both cases cracks were nh m~1 Tp
_ e n& = c'g. Let sa w cle rly cf Llu pIcpagatir.g type as opposc3 to the " disk geometry" associated with the exterml
" strawberry" examinad. Thus there was na evideme for tMsc additioral cracks at the other two locations to be " running out of gas." The possibility tlat the cracks in the flaroi region of the first safe ord were related positively to oxygen comentration must be rejectcd in vica of the narrowness of the crevice, i.e.
the high surface to volume ratio for the solution would permit the oxygen to deplete rapidly.
The observation of the lorgitudiml crack in the seconi core spray nozzle frcm the GE investigation suggest that the residual stresses nay be unprcdictable and significant.
- 6. The strong incentive for repair at the present time is relatcd also to the fact that repairs later will be incrmsirgly difficult cwing to the accumulation of radioactivity. A failure several years herce will be increasirgly difficult to repair and will result in groater risks to personnel tlun perfonning the repair inrr.odiately. Knile this point is obvious, it should be considered relative to the very high probability that failures will occur unless repairs are nude.
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- 7. I do not believe Llut a p cgrm of interinn inspcction 1 is sufficient to prevent the o;carre2ce of a scrious j crack. The initial cracks obscrved at IM occurral within three months. It is nusomb!c tlut a cracking system v;hich .
starts sloaly ard ruuin urdcto:tcd airly could, within a j; short tim, begin pcepgating at a very rapid rate. i l
8 There is no lucis for the fact tlnt the reactor syston must l be dymmic (i.e. Irating, conting, or otherwice contortim) l for crach to promote. The caupanents can be essentially still, and the residual stre sea 1.ould be sufficient for cracks to initiate anl prolmgale. j
- 9. The significance of the transgranular cracks startirn fran the l i
inside of the cafa e'd of the rwon1 core spray nozzle at ;
IGP is rot clear. They were citarly caused by simultaneous l presence of chlorid: ions a:d c:;ygen at the 1-10 ppn level. l Ilowever, it is not clmr at dat tilue chloride was present. l The mtural yaestion here is schy vns more clchensive transgrarclar
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not observcd in otLE parts of the systcm, i.e. in the othar core spray nozzle. This proMea could be rcasonably associated with only this seccad core spray line. Ibwever, tlus issue l
l is rnt clcar. There is an inantive for pursuirg this natter further.
- 10. r'amn oc thn y rtra H rn 7 u tM yen: im ef trangranular cracks frcm the outside despite the reasonability of occasiona1 contamination proLably results from the fact that t]n metal surfaces when hot are dry ard when ecol and wet are not sufficiently varm for cracks to propagate.
Concluding Rainrks The stress corrosion problea is characterizcd 17f its incrcdibility.
After all, the Imterial is " stainless" ard does not corrog,gtgay !
occur once but after. all,an irdivigaljailure;i does not 'rchp7.4t an j
epidonic.* This subconcious belief has anesthetizcd both technical perspcctive og expert- and the practical judgment of engineering mamgcment. I belicve it is time for the AEC to rublish a decisive instruction tlut all sensitizcd
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stainless steel must be clilain;tod. Unless such action is taken stmunrily, the roactor in3ustry jeopardizes itself in terms of a nnjor failure. That such a failure v.ould be grevious not only to the A1C tut also the country s already deficient electrical pcwer goes without saying.
While tha above pragraph as well as the entire letter is not constructcd in gaantitative terns and is rhetorical in place'it portrays the seriousness with which the problon must be considercd acted uoon.
It is never possible to inve anywhere naar sufficiently quantitative infornntion to unke such ergineering decisions.
,I urge you to iInplanent those rccaimenhtions without delay.
S erely,
- This is in jest but represents, unfortumtely gq3 lah R. . . tachle prevailing opinion.
_ _ _ _ _ _ _ _ _ _ _ _ Consultant
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