Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
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- Public Service Electric and Gas Company Stanley: La Bruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations June 16, 1989 NLR-N89117 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION BULLETIN 88-09 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Attached is one copy each of the following Combustion Engineering proprietary documents:
TR-ESE-737, Rev~ 00, Salem ICI Thimble Tube Flow Induced Vibration Test Program Copy No. 000014 TR-ESE-746, Rev. 00, Salem ICI Thimble Tube Evaluation of Impact of Reduced Height of Sleeve on Wear Resistance Copy No. 000006 Additionally, one copy of the following non-proprietary documents are attached:
E-71186-165-002, Rev. 03, FTTC Assembly Drawing Table X, page 24, Review of the Wear and Galling Characteristics of Stainless Steel, AISI Cover page and pages 121 and 122 of Corrosion and Wear Handbook for Water Cooled Reactors, U.S. AEC These documents are being provided directly to Mr. J. Stone, NRC Licensing Project Manager pursuant to a request made during a recent NRC site visit by Mr .. Shou-Nien Hou NRR/EMEB and Mr. G.
DiGrassi, BNL. Since these documents were requested as a result of a site visit and are not directly related to a licensing action, only one copy of the proprietary version and no non-proprietary versions are being provided.
990616 9002002oc~ 05000272 8p'.DR ADO n PNU p;-
Document Control Desk 2 6-16-89 NLR-N891i7 As noted two of above these documents are considered proprietary by Combustion Engineering and pursuant to 10CFR2.790 should be withheld from public disclosure. Affidavits from Combustion Engineering stating that the proprietary nature of these documents are attached.
Should you have any questions, please feel free to contact us.
Attachments C Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
AFFIDAVIT PURSUANT TO 10 CFR 2. 790 Combustion Engineering, Inc. )
State of Connecticut )
County of Hartford ) SS I, A. E. Scherer, depose and say that I am the Director, Nuclear Licensing, of Combustion Engineering, Inc. , duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2. 790 of the Commission's regulations and in conjunction with the application of Public Service Electric and Gas Company for withholding this information.
The information for which proprietary treatment is sought is contained in the following document:
TR-ESE-737,. Rev. O, "Salem ICI Thimble Tube Flow Induced Vibration Test Program Test Report" This document has been appropriately designated as proprietary.
I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.
Pursuant to the provisions of paragraph (b) ( 4) of Section 2. 790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.
- 1. The information sought to be withheld from public disclosure concerns the test results supporting the effectiveness of wear sleeves in reducing in-core instrumentation thimble tube wear in Westinghouse reactors, which is owned and has been held in confidence by Combustion Engineering.
- 2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.
- 3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. .Combustion Engineering has a rational basis for determining the types of information customarily held* in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F. M. Stern to Frank Schroeder dated December 2, 1974.
This system was applied in determining that the subject document herein are proprietacy.
- 4. The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2. 790 .with the understanding that it is to be received in confidence by the Commission.
- 5. The information, to the best of my knowledge and belief, is* not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
- 6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:
- a. A* similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.
- b. Development of this information by C-E required hundreds of man-hours of effort and tens of thousands of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating equivalent information.
- c. In order to acquire such information, a competitor would also require considerable time and inconvenience developing wear sleeve designs for reducing in-core instrumentation thimble tube wear in Westinghouse reactors.
- d. The information required significant effort and expense to obtain the licensing approvals necessary for application of the information. Avoidance of this expense would decrease a competitor's cost in applyi~g the information and marketing the product to .which the information is applicable.
- e. The information consists of the test results supporting the effectiveness of wear sleeves in reducing in-core instrumentation thimble tube wear in Westinghouse reactors, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position pf Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.
- f. In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included. The ability of Combustion Engineering's competitors to utilize such
information* without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.
- g. Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development.
In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.
Further the deponent sayeth not.
A. E. Scherer Director Nuclear Licensing Sworn to before me this '1Pv day o~.1 /919
AFFIDAVIT PURSUANT TO 10 CFR 2. 790 Comb:ustion Engineering, Inc. )
State of Connecticut )
County of Hartford ) SS I, A. E. Scherer, depose and say that I am the Director, Nuclear Licensing, of Combustion Engineering, Inc. , duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2. 790 of the Commission's regulations and in conjunction with the application of Public Service Electric and Gas Company for withholding this information.
The information for which proprietary treatment is sought is contained in the following document:
TR-ESE-746, Rev. O, "Salem ICI Thimble Tube Evaluation of Impact of Reduced Height of Sleeve on Wear Resistance" This document has been appropriately designated as proprietary.
I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.
Pursuant to the provisions of paragraph (b) ( 4) of Section 2. 790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.
- 1. The information sought to be withheld from public disclosure concerns the evaluation of the effectiveness of shortened wear sleeves, as compared to the original, unsleeved in-core instrumentation thimble tube configuration in Westinghouse reactors, which is owned and has been held in confidence by aombustion Engineering.
2*. The information consists of test data or other similar data concerning a process, method or component~ the application of which results in substantial competitive advantage to Combustion Engineering.
- 3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold cert~n types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F. M. Stern to Frank Schroeder dated December 2, 1974.
This system was applied in determining that the subject document herein are proprietary.
- 4. The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2. 790 with the understanding that it is to be received in confidence by the Commission.
5'. The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
- 6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:
- a. A_ similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.
- b. Development of this information by C- E required hundreds of man-hours of effort and thousands of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating equivalent information.
- c. In order to acquire such information, a competitor would also require considerable time and inconvenience developing a shortened wear sleeve design for reducing in-core instrumentation thimble tube wear in Westinghouse reactors.
- d. The information required significant effort and expense to obtain the licensing approvals necessary for application of the information. Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable.'
- e. The information consists of the evaluation of the effectiveness of shortened wear sleeves, as compared to the original, unsleeved in-core instrumentation thimble tube configuration in Westinghouse reactors, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.
- f. In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.
The ability of Combustion Engineering's competitors to utilize such
information without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.
- g. Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development.
In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.
Further the deponent sayeth not.
~
A. E. Scherer Director Nuclear Licensing Sworn to before me this?ZA.-day ~ l'/8'7
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TABULATION OF BABIC DATA 121 FOR~WORD TO TABLE 7-3-WEAR TEST Most of the material combinations considered 11uitable DATA for service application possessed a wear factor less than 100 mg per pound load per million cycles.
Tut Conditions Special Notu Wear factors were determined by means of two different wear test units. One unit, referred to as the (1) The martensitic stainless steels were tested in the piston-cylinder test rig, pr"lduces wear by means of hardened condition. For the precipitation-hardening linear reciprocating motion. The other unit, referred alloys the symbol PH designates the hardened condi-to as the journal-sleeve test rig, produces wear b\* tion, and SA indicates the solution annealed condition.
means of rotational movement. The majority of th~ Ceramics, cermets, and various miscellaneous mate-tests were conducted in oxygenated water containing rials were tested in the as-received condition. The JO to 30 cc of oxygen (STP) per kilogram of water. remaining metals and alloys were tested in the The hydrogen content. for wear tests in hydrogenated solution annealed condition. All references to chro-water:varied from 200 to 500 cc (STP) per kilogram of mium plating are to plating applied by an approved water. For both environments initial electrical resis- supplier. (See ch. 13.)
tivity of the water was 500,000 ohm-cm or greater. (2) The surface finish of untested samples ranged from Tests were normally run for 500,000 cycles. Details of 8 to 16 microinch (rms).
the test procedures are given in chapter 5 on testing (3) The bearing combinations are arranged so that the procedures. entry in the "materials" column is the moving ele-Interpretation of Wear FaciorB ment of the wear couple unless otherwise indicated.
The combinations are listed in order of increasing Wear factors for both tests were determined by meas- wear. A complete cross index of all couples can be uring the weight loss per pound load per million cycles. found in the general index.
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122 CORROSION AND WEAR HANDBOOK FOR WATER-COOLED REACTORS Vlill TIST DiTi TJpe or Test. .&dditi"n*
Mateir'ial... VerllUS fist.an JOllZ'Dal. -
~,4-'-
pn pn
~
- °"
T!llP* tom llNr (pm.) Factor
~
AlSI 304 SS or
'347 SS
-~
RT-SN Chrcmium Ag Brazing lllo7 As Plated St.ellit.e Ho. 6 Haynes 25 (Cold Worked)
(.0005* x x
x x
x x
x x
500 soo 500 10 8 ~
8 8
92 170 210
- I 500 H~~ll No. 21 (SA) lt lC 500 8 240 Lead lC Jt 200 8 270 S-1".onel lC x 500 8 400 USS 1~8 W (PH) Jt x 500 8 lOl.O Lead x x 500 10 2790 AISI 301.SS lt x 500 8 ~
17-4 PH (SA) lt x 500 8 lo5 5-Monel x x 500 10 aeized BT Air Brazinir Alloy *" lt x i;oo 10 4 RT-SN Ag Brazing Alloy tiff lt x 500 10 4 Lead lC x 500 10 4 I AISI 410 SS stellit.e No. 3 x lt 500 8 16 stellite No. 3 x x 500 10 140 stellite Ho. 6 x Jt 500 10 145 AISI 410 SS x x 200 10 290 AISI 410 SS lt x 500 10 380
- AISI 410 SS Graplli tar
- Zl2U7' u thi* 001,_ 1* .mq unless othendse indicated.
14 (1) eJ.mmt or tu 1P8G' ooap1e x x 500 10 145
- Wear Factor - Milligram.s per pound load per million cycle 11
- nnployed in service *** Handy &> Harman (1) Ho T&l.id vear !actor,1 hovever, this combination vaa succeaafully utilizod *
.. ~*
TABLE, WEAR COMPATIBILITY OF DISSIMILAR CORROSION-RESISTANT ALLOY COUPLEs<10 1 Stainless steel couples - weight loss, mg/1,000 cycles l Type Type Nltronlc Nltronlc Nltronlc Type Alloy 304 316 517400 32 50 60 440C (Rockwell hardness} (B 99} (B 91) (C 43} (B 95} (B 99} (B 95) (C 57)
Type 304 @
Type 316 10.5 12.5 S17400 24.7 18.5 52.8 Nitronic 32 8.4 9.4 17.2 7.4 Nitronic 50 9.0 9.5 15.7 8.3 10.0 Nitronic 60 6.0 4.3 5.4 3.2 3.5 2.8 Type 440C 4.1 3.9 11.4 3.1 4.3 2.4 3.8 Other dlsslmllar corrosion-resistant couples-weight loss, mg/1,000 cycles Siiicon Chrome Stelllte Monel Waukesha Alloy bronze plate 6B K-500 88 (Rockwell hardness} (B 93} (C 48} (C 34) (B 81}
Type 304 (B 99) 2.1 @ 3.1 8.1 S17400 (C 43) 2.0 3.3 3.8 34.1 9.1 Nitronic 32 (B 95) 2.3 2.5 2.0 7.6 Nitronic 60 (B 95) 2.2 2.1 1.9 22.9 8.4 Type 316 (B 91) 33.8 9.6
- a Monel K-500 (C 34) 30.7 9.3 Test conditions: V2-in.-dia. crossed (90°) cylinders: no lubricant; 16-lb load: 105 rpm: room temperature:
120-grit finish: 10.000 cycles: specimen degreased in acetone: duplicate tests: weight loss corrected for density differences. Hardnesses given apply to both axes.
TABLE.XI GALLING RESISTANCE OF STAINLESS STEELS 11°>
Button Material Block Condition Iii Nominal Hardness Nitronlc Nitronic Material (Brlnell) 410 416 430 440C 303 304 316 517400 32 60 Type410 Hardened & Stress Relieved (352) 3 4 3 3 4 2 2 3 46 50+
Type 416 Hardened & Stress Relieved (342) 4 13 3 21 9 24 42 2 45 50+
Type 430 Annealed ( 159) 3 3 2 2 2 2 2 3 3 36 Type 440C Hardened & Stress Relieved (560) 3 21 2 11 5 3 37 3 50+ 50+
Type 303 Annealed ( 153) 4 9 2 5 2 2 3 3 50+ 50+
Type 304 Annealed ( 140) 2 24 2 3 2 2 2 2 30 50+
Type 316 Annealed (150) 2 42 2 37 3 2 2 2 3 38 S17400 H 950 (415) 3 2 3 3 2 2 2 2 50+ 50+
Nitronic 32 Annealed (235) 46 45 8 50+ 50+ 30 3 50+ 30 50+
N1tronic 60 Annealed (205) 50+ 50+ 36 50+ 50+ 50+ 38 50+ 50+ 50 J Values si1own are unlubncated threshold galling stress (106 psi) for the "button and block" galling test. Condition and hardness apply to both the button and the blank material. Tests were terminated at 50 x 106 psi. so values given as 50+ indicate the samples did not gall.
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