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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212B1681999-09-13013 September 1999 Forwards Insp Repts 50-275/99-12 & 50-323/99-12 on 990711- 08-21.Four Violations Being Treated as Noncited Violations ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H6181999-07-27027 July 1999 Forwards Insp Repts 50-275/99-07 & 50-323/99-07 on 990503- 0714.Apparent Violations Being Considered for Escalated Enforcement Action ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot IR 05000275/19980121999-01-13013 January 1999 Informs That Insp Repts 50-275/98-12 & 50-323/98-12 Have Been Canceled DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld ML20195G5161998-11-16016 November 1998 Forwards Insp Repts 50-275/98-16 & 50-323/98-16 on 980913- 1024.No Violations Noted ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236T2931998-07-24024 July 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities for 5 Yrs.Order Being Issued Due to Falsification of Info on Application to Obtain Unescorted Access to PG&E Plant ML20236T3431998-07-22022 July 1998 Forwards Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.Apparent Violations Identified & Being Considered for Escalated Enforcement Action ML20236J2251998-07-0101 July 1998 Ltr Contract,Task Order 232 Entitled, Review of Callaway, Comanche,Diablo Canyon & Wolf Creek Applications for Conversion to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 IR 05000275/19980051998-04-17017 April 1998 Forwards Insp Repts 50-275/98-05 & 50-323/98-05 on 980202-06 & 23-27 & 0302-18.No Violations Noted.Insp Focused on Resolution of Previous NRC Insp Findings & Included Review of Issues Identified During Architect/Engineering Insp Rept ML20203G0371998-02-25025 February 1998 Forwards Revised Copy of NRC Form 398, Personal Qualification Statement - Licensee, (10/97) Encl 1,which Has Been Revised to Reflect Current Operator Licensing Policy DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld ML20199H6691998-02-0202 February 1998 Ack Receipt of ,Transmitting Rev 18,change 11, to Plant Physical Security Plan,Submitted Under Provisions of 10CFR50.54(p).Role of Video Capture Audible Alarm Sys Needs to Be Addressed in Security Plan,Per 980123 Telcon DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld IR 05000275/19970181997-10-31031 October 1997 Forwards Insp Repts 50-275/97-18 & 50-323/97-18 on 971006- 10.Insp Verified That Liquid & Gaseous Radioactive Waste Effluent Mgt Program Was Properly Implemented.No Violations Noted DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML20134H6271997-02-10010 February 1997 Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5) ML20134K3421997-02-0606 February 1997 Conveys Results & Conclusions of Operational Safeguards Response Evaluation Conducted by NRR at Plant,Units 1 & 2, on 960909-12.W/o Encl ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) ML20129J4001996-10-18018 October 1996 Forwards Order Approving Corporate Restructuring by Establishment of Holding Company & Safety Evaluation NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl ML20129G6121996-09-24024 September 1996 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App C,E,F & G.Documents Available in Pdr.App E,F & G Documents Partially Withheld Ref FOIA Exemptions 4 & 6.App D Record Listed as Copyright DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld 1999-09-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld ML20100L4631996-02-23023 February 1996 Forwards Response to NRC Enforcement Action 95-279 Re Violations Noted in Insp Repts 50-275/95-17 & 50-323/95-17 on 951021-1208.Corrective Actions:Directive Was Issued to Plan 2R7 W/Six Day Work Schedule DCL-96-036, Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr1996-02-20020 February 1996 Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr ML20097E9341996-01-25025 January 1996 Forwards Public Version of EPIP Update for Diablo Canyon Power Plant,Units 1 & 2 DCL-95-272, Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training1995-12-11011 December 1995 Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training DCL-95-264, Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5))1995-12-0606 December 1995 Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5)) ML20094M6001995-11-21021 November 1995 Forwards Final Rept of Investigation & Analysis of Event 29257 Re Substandard Fastner Processed & Sold by Cardinal Industrial Products,Lp,So That Customers Can Evaluate Situation in Light of 10CFR21.21(a)(1)(ii) & (b)(1) DCL-95-204, Forwards Proposed Changes to Physical Security Plan.Encl Withheld1995-09-19019 September 1995 Forwards Proposed Changes to Physical Security Plan.Encl Withheld DCL-95-199, Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan1995-09-14014 September 1995 Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan ML20087A0471995-07-28028 July 1995 Forwards Security Safeguards Info in Form of Change to Proposed Draft Plant Security Program.Encl Withheld DCL-95-153, Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo1995-07-27027 July 1995 Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo DCL-95-134, Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d)1995-07-0505 July 1995 Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d) ML20086H5461995-06-29029 June 1995 Forwards Final Exercise Rept for 931020,full Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response plans,site-specific to Plant.No Deficiencies Noted DCL-95-046, Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld1995-02-28028 February 1995 Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld DCL-95-039, Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo1995-02-23023 February 1995 Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo ML18101A5671995-02-17017 February 1995 Informs of Improper Presentation of Jet Expansion Model in Bechtel Technical rept,BN-TOP-2,Rev 2 Design for Pipe Break Effects Issued May 1974.NRC May Need to Consider Evaluating Consequences of Potential Misapplication of Expansion Model ML18101A5681995-02-17017 February 1995 Requests NRC to Clarify Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 LCO Under Circumstances as Ref in in 95-10.Subj in Re Postulated Slb W/Potential to Render One Train of Ssps Inoperable ML18101A5741995-02-17017 February 1995 Requests Clarification of Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 Limiting Conditions for Operation Under Circumstances Described in Info Notice 95-10 DCL-95-033, Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures1995-02-13013 February 1995 Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures DCL-95-013, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo1995-01-24024 January 1995 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo DCL-94-258, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B1994-11-21021 November 1994 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B 1999-06-25
[Table view] Category:UTILITY TO NRC
MONTHYEARDCL-90-202, Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.91990-08-0707 August 1990 Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.9 ML20043A4131990-05-17017 May 1990 Forwards Response to Violations Noted in Insp Repts 50-275/90-02 & 50-323/90-02 Re Unauthorized Individuals Gaining Access to Vital Areas & Failure to Protect Safeguards Matl.Response Withheld ML20042G6491990-05-10010 May 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML16341F6901990-04-26026 April 1990 Forwards Public Version of Rev 9 to Corporate Emergency Response Plan 4.3, Radiological Analyses & Protection. ML17083C2491990-04-0202 April 1990 Forwards Response to Questions on Geology/Seismology/ Geophysics/Tectonics in long-term Seismic Program Final Rept.Proprietary Data Withheld (Ref 10CFR2.790).W/one Oversize Drawing ML20012E2261990-03-26026 March 1990 Forwards Rev 17 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21) ML20042H0421990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F6431990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Emergency Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F5941990-02-14014 February 1990 Forwards Public Version of Rev 11 to EPIP EP G-4, Personnel Accountability & Assembly. W/900305 Release Memo ML16341F5581990-02-0606 February 1990 Forwards Proprietary WCAP-12495 & Nonproprietary WCAP-12496, Review of Flow Peaking & Tube Fatigue in Diablo Canyon Units 1 & 2 Steam Generators Per El Murphy Aug 1989 Request ML16341F5401990-01-30030 January 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EP M-1 & EP M-6 & Rev 13 to EP G-2S1.W/900215 Release Memo ML16341F5421990-01-29029 January 1990 Forwards Public Version of Rev 7 to Corporate Erpip Update ML20005G0521990-01-0909 January 1990 Forwards Rev 3 to Safeguards Contingency Plan,Per Generic Ltr 89-07.Rev Withheld (Ref 10CFR73.21) ML16341F4351989-11-13013 November 1989 Forwards Public Version of Epips,Consisting of Pages 15,29 & Test Data Sheets to Rev 10 to EP M-4, Earthquake, & Pages 32-1 & 32-3 to Rev 16 to EP M-6, Nonradiological Fire. W/891205 Release Memo ML20246E6061989-08-16016 August 1989 Forwards Endorsements 10 & 11 to Nelia Certificate N-74 & Maelu Certificate M-74 & Endorsements 7 & 8 to Nelia Certificate N-76 & Maelu Certificate M-76,respectively DCL-89-201, Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form1989-07-28028 July 1989 Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form DCL-89-183, Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1989-07-0606 July 1989 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) DCL-89-149, Requests Renewal of Approval of QA Programs for Radioactive Matl Packages1989-05-30030 May 1989 Requests Renewal of Approval of QA Programs for Radioactive Matl Packages ML20244B4881989-04-0707 April 1989 Forwards Endorsement 35 to Maelu Policy MF-103 & Endorsements 65 & 116 to Nelia Policies NF-228 & NF-113, Respectively DCL-89-051, Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo1989-03-0202 March 1989 Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo DCL-89-042, Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21)1989-02-23023 February 1989 Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21) ML20235J2191989-02-17017 February 1989 Forwards Endorsements,Including Endorsement 3 to Nelia Certificate NW-132,Endorsement 3 to Maelu Certificate MW-73, Endorsement 4 to Nelia Certificate NW-51 & Endorsement 4 to Maelu Certificate MW-135 ML16341E8821988-11-30030 November 1988 Forwards Proprietary WCAP-12064, Diablo Canyon 1 & 2 Evaluation for Tube Vibration Induced Fatigue. All Five Tubes Requiring Corrective Action Removed from Svc During Unit 2 Refueling Outage.Rept Withheld (Ref 10CFR2.790) DCL-88-277, Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope1988-11-18018 November 1988 Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope DCL-88-216, Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support1988-09-0202 September 1988 Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support ML16342B4691988-08-0101 August 1988 Forwards Proprietary WCAP-11312, Westinghouse Owners Group Tech Spec Subcommittee Reactor Trip Breaker Maint/ Surveillance Optimization Program. Rept Withheld (Ref 10CFR2.790) DCL-88-128, Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21)1988-05-12012 May 1988 Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21) DCL-88-095, Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21)1988-04-19019 April 1988 Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21) DCL-88-051, Forwards Rev 16 to Physical Security Plan.Rev Withheld1988-03-0404 March 1988 Forwards Rev 16 to Physical Security Plan.Rev Withheld ML20151G1181988-02-22022 February 1988 FOIA Request for Documents Re ACRS Subcommittee Meetings on 750218-19 Re Plant ML20147E3651988-02-10010 February 1988 FOIA Request for Documents Re NRC 750318 Summary of ACRS Subcommittee Meeting on 750218-19 DCL-87-269, Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21)1987-11-0909 November 1987 Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21) ML20236N5361987-11-0909 November 1987 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments 860323-870322. Rept Same as Reporting Interval of Annual FSAR Update Rev ML20236H9691987-10-26026 October 1987 Forwards Endorsement 25 to Maelu Policy MF-103 & Endorsement 55 to Nelia Policy NF-228 DCL-87-249, Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util1987-10-13013 October 1987 Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util DCL-87-216, Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation1987-09-0808 September 1987 Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation DCL-87-202, Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo1987-08-13013 August 1987 Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo DCL-87-159, Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21)1987-06-30030 June 1987 Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21) DCL-87-146, Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21)1987-06-25025 June 1987 Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21) DCL-87-129, Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-11987-06-0808 June 1987 Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-1 ST-HL-AE-2035, Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl1987-04-30030 April 1987 Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl ML20207R4571987-03-13013 March 1987 Forwards Endorsements 52 & 110 to Nelia Policies NF-228 & NF-113,respectively DCL-87-045, Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised1987-03-11011 March 1987 Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised DCL-87-042, Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-0031987-03-0909 March 1987 Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-003 DCL-87-041, Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21)1987-03-0505 March 1987 Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21) 05000275/LER-1985-014, Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip1987-03-0303 March 1987 Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip DCL-87-024, Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-271987-02-12012 February 1987 Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-27 ML20211F5121987-02-11011 February 1987 Informs That Lt Gesinsky Has Become Seriously Ill & Will Not Be Able to Testify,As Witness,On Behalf of Util.Ee Demario Will Replace Lt Gesinsky as Witness.Prof Qualifications Encl DCL-87-014, Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage1987-01-28028 January 1987 Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage DCL-87-006, Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler1987-01-12012 January 1987 Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler 1990-08-07
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PACIFIC GAS AND ELECTRIC C O M PANY EO*J43 l 77 8EALE STREET . SAN FRANCISCO, CALIFORNIA 94106 . (415)781 4211 . TWX 910-372 6587 J. O. InCHUYLER v<t e. asset.t
...........t.
February 29, 1984 PGandE Letter No.: DCL-84-081 Mr. John B. Martin, Regional Administrator U. S. Nuclear Regulatory Commission, Region Y 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-76 Diablo Canyon Unit 1 SSER 21 - Allegation 99, Bostrom-Bergen Metal Products
Dear Mr. Martin:
Enclosed is PGandE's Materials Sampling Program interim report for Bostrom-Bergen/Meddco-Metals. This interim report provides a status of PGandE's investigation and sampling program results to date concerning the all,egations made by former employees of Bostrom-Bergen/Meddco Metals, a l structural steel fabricator for Diablo Canyon.
Kin'dly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely, 6,
p ,p .. v . achuyler e Enclosure ,
cc: T. W. Bishop ,
i D. G. Eisenhut H. E. Schierling Service List 8603310016 860123 lM PDR FOIA DEVINE84-744 PDR -
I
1 F
PGandE Letter No. DCL-84-81 ENCLOSURE ,
INTERIM REPORT OF BOSTROM-BERGEN/MEDDCO-METAL MATERIALS SAMPLING PROGRAM Introduction
- Investigation into the allegations regarding quality practices of Bostrom-Bergen/Meddco-Metal (BB/MM) is currently.being conducted. The scope i
and status of this documentation review are described in PGandE Letter DCL-84-051, dated February 10, 1984. To provide additional confidence in the adequacy of the materials supplied by BB/MM, PGandE has initiated a field sampling program which is described herein.
Bostrom-Bergen and its subsidiary, Meddco Metals, supplied certain materials to the Diablo Canyon Power Plant (Diablo Canyon) from 1969 to the present.
These materials are best described as miscellaneous metals that were used in a variety of applications and include both individual pieces and fabricated assemblies.
. A preliminary plan for reinspecting the BB/MM material was prepared and presented to the NRC's Region V personnel on February 23, 1984. This plan, which is attached as Appendir A to this submittal, has been finalized and is currently being used to direct the ' reinspection of a sample of BB/MM material installed at Diablo Canyon. The plan may be modified upon further review.
This submittal provides an interim report on the results of the reinspections perf.ormed to date.
l-Scope-Items that are being reinspected were selected by reviewing all shop drawings and selected purchase orders involving BB/MM material shipped to the jobsite j since 1969. A complete list of all major BB/MM supplied items including their i
material type and safety application will be provided ~1h a final report.
The specific items selected for reinspection were from Class I components which would demonstrate that special steels were used at locations where they y were required and that special fabrication techniques (e.g., heavy welding) vere adequately performed. The selected items are listed in Tatle 1.
In addition to the items described above, four bulk material items were added to the sample and are also listed in Table 1. These. samples are from the Class I bulk materials which a former Bostrom-Bergen inspector alleged that he falsely documented inspections. As addressed in Section 4.1 of the report L _1 0384d/
attached to the PGandE February 10 letter (DCL-84-051), the do' cumentation associated with all of the materials (Class I and non-Class I) inspected by this Bostom-Bergen employee was reviewed.
A few significant items supplied by BB/MM are excluded from this reinspection '
Program. These items were the subject of other recent reinspections and include pipe rupture restraints, the structure enclosing the condensate Polishing system and the reverse osmosis system components. Summaries of these previous reviews, which found the subject materials to be acceptable, are provided in Appendir C to this submittal.
The material reinspections now being performed can be grouped into two
- categories: material verification and fabrication verification. Material verification is being accomplished by hardness testing, which indirectly measures the material's tensile strength. For cases in which further investigation is necessary, analysis of the material's elemental composition will be performed.
I The second category, fabrication verification, is being accomplished by (1) general inspections,' (2) visual weld inspections, and (3) NDE weld inspections. General inspections compare existing materials to shop drawings to determine geometrical and dimensional conformance. Visual weld inspections are performed on all sampled (shop) welds performed by BB/MM and follow the AWS criteria. Appendix B to this submittal contains the visual weld inspection criteria being used in this reinspection. For items requiring heavy shop welds (these are identified in Table 1), NDE weld inspections are accomplished as follows; documentation of NDE inspections by an independent laboratory are reviewed. If acceptable NDE reports are not available, new NDE inspections will be performed. No new NDE inspections have yet been required.
To date, most of the selected samples have been completely reinspected. Of the data compiled in these reinspections, most has been reduced and evaluated.
Results to Date Table 1 contains the reinspection results compiled for each item sampled.
While the sampling has not been completed, the following trends and results are apparent:
.a) General inspections are finding that the existing geometries and dimensions are in conformance with the shop drawings.
b) Hardness tests are indicat'ing that correct materials were provided.
c) Visual weld inspections are indicating that BB/MM welding meet design requirements. ,
d) Records from the NDE documentation research show that full penetration welds by BB/MM are satisfactory.
0384d/
s ,
e) Bulk materials identified as a result'of the Bostrom-Bergen inspector's allegations are being found acceptable in the appropriate inspection categories. .,
The reviews addressed above and in Table 1 have not yet identifie& the time ,
spans covered by the selected samples. The adequacy of the sample with respect to the time span will be determined and addressed in the Final Report. If required, additional items will be added to the sample and will be included in the final report. -
Summary The material and fabrication reinspections performed to date indicate that the BB/MM supplied materials are in conformance with requirements. Based upon these results it is expected that the 10 to 15 percent of the sample items which still remain to be reinspected, will not alter this conclusion. Thus these reinspections,' in combination with the previous reinspections addressed in Appendix C, provide assurance that the BB/MM materials furnished to Diablo Canyon are acceptable. After completion of the reine- Stion effort, a final report will be prepared and submitted to the NRC.
O O
e e
0384d/
9 TABLE 1 ; -
Bostrom-Bergen/Meddeo Metal Ite .s Sampled and Reinspection Results I SAMPLED ITDI MATERIAL VERIFICATION FABRICATION VERIFICATION i 8 8/101 Brinell Visual General Piece Piece Hardness Tenaile Spectrol General Veld ,
Description Desc ription Mark Reading Strength Results Anslysis Results Conformance Results Inspection Resulte NDE Results Rema rks ;
Cratainment Unit #1 LP #1, No exposed shop -
Itterior El. 94'-O* Pip
- B343 12 0 59 AS/ OK. (2.) -
(f)
(l) - b)- , weld on this Embed Plates Rupture Diece.
Restraint Embed . j
( A-%) -
Unit #1 LP #1, No exposed shop
^*
El. 94*-O* PiP
- H 343 Rupture lig . 57 ksi og (a) -
II) "
(I) -- ' III - _ - weld on this piece. .
j Restraint Embed (A-36) .
Unit #1 LP #3, No encosed shop k;,9"l'* r1344 las us xsi og (a) -
(I) -
(1) - - --- ~- il ) = jy" th" Restraint Embed * '
( A-%) l Unit #1 LP #4, No exposed shoo El. 94*-O* Pipe rJ344 Rupture 12(a GE ASI OK (E) -
(I) -
(1) -
(l) --
weld on this pfece.
Restraint Embed
( A-%) .
I Unit #1 LP #4, No exposed shoo (
El 94*-0* Pipe g343 Rupture g g 7, f, g g3; og~ (p,) . .
(l)
(1) .
(1) . ~
weld on this piece. I Restraint Embed (A-X) .
Unit #1 LP #2, No exposed shoo Steam Generator Lateral Support 822) f47 7 2 AS/ og (2. ) '
(f) -
(l) -
(I L___ - . weld on this olete, ,
at El. 115'-0*
( A-%)
Unit #1 LP #1, No exposed shop Steam Generator 8221- /Sg 16 kil OK (2). -
(1) -
(l) -
(I) -
weld on this Lateral Support A piece.
at El. 115'-0*
(A-36)
~
038Sd/
l TABLE 1 i
Boetree-Bergen/Neddeo Metal Itsee Saepted and Retaspectica Beaults a
. SAllP1.ED ITBE IIAft3TAL VERIFICATI0s FABRICATION VERIFICATION RS/let Brinell General Piece Piece liardnese Tene11e Visual 4
Description Description Spectrol General Wold IEark Reedtog Strength Resulta Analyste leeulte ao Con formance Beaults inspection Resulte 598 Seoulte Beme rke containsomt Unit #1 LPfle Interior 31 94'-0* N343 l'*AacherBolte mh 357 -
ok ,( 2) X oK (l)
Pipe Rupture _,,
~__ fl) -
l Beetraint(A490) l Unit #1 LPfl.
. El 94*-0* N343 Pipe Rupture 347 .OK (2) ._ _X .,_ . _ . O K _
A-mle (l) _ _. (O Restrelat (A490) .
Unit il LPfl.
- 81. 94'-o* 8M3 Pipe Rupture ink 347 -
ex (z) -
x ok (1) -
() -
Bestrelat (A490)
B1 94'-o" 8543 3Gi Pipe Rupture A.4
'-oK. (2) -
X of (f) -
(1) -
Bestrelat (A490) --
Unit #1 LPf1, 81 94*-0*
c225 350 -
on Pipe Supture asetraint (A490)
(2) -
x ok (l) -
- (s) -
6 Unit il LPfl.
P1 R re ( -
Bestraint (A490)
CM (l ) , , . _ _ _ (l) -
I 1
- Unit #1 LPfl.
sl. 94*-o* AZZo 3f4 (2I t -
Steam Generator *i OK -
X og (i) -
Vertical Support -
(I) -
(A490)
Unit #1 LPfl, ri. 94 -o- Ano wz. -
ox (2) Y cx Steam Cenerator .g4 (s) -
(0 -
Vertical Support (A490) ,
I i.
0385d/
2
e '
. .~
l . .
TABLE 1 Rostrom-Rergen/Neddco Metal itses Sempted and Retaspection Beaulte
- SAMPLED 1798 MATERTAL VERIFICATIOR FABRICATIOR YERIFICAff0R i
RE/IDE Brinell General . Piece Piece Hardnese Tensile Visual Desc ription Desc rip tion Spectrol Ceneral Weld Mark Reading St reng th Resulte Analysis Resulte con formance Results Tampaction Resulte NDE Resulte Rese rke costelament Unit #1 LPfl.
- 31. 94*-o* A220 Interior hr Bolu Steen Generator 2 33 4 _
og (g) .
_ ,y og (g} , , _ , , , , , , _ , (Q_,-
Vertical Support
( 4 90)
Unit #1 LPit, st. 94'-o* Azzo (3)
Stesa Generator .gg (3) x og (g) _
(g) , -
Vertical Support (A490) unit #1 LPfl.
Bl. 94'-o* AZZo 354 Steam ce retor 3 OK (2) -
X OK _.. (I) -
(1) -
Vertical Suppo*rt (A490)
Catt #1 LPfl.
al. 94'-o* A220 Steam cenerator 34 328 -
ofC (2) -
X OK Vertical Support (i) -
(t)___-
(A490)
Unit #1 LPit, al 94*-o* AZZ8
! 325 ok i
/
Ste cenerator Vertical Support 4 (2) -
X og (t) -
(s) -
(A490)
Unit #1 LPil.
l ~
3 eaa emerator Vertical Support
~
05 ' ~
(N- ~
l (A490) .
l Unit #1 LPf2 n1. 94 -o* rip. 6343 on
(a) -
x og it) -
U). -
Restratat (A490) f I
0385d/
l
~
i TABLE 1 I
Rostroe-Bergen/Neddeo Natal Items Sampled and Reinspection Resulte SANPLED 1758 NATER 1 VERIFICA?!0g FABRICATIOS VERIFICA?!05 General Piece BS/let Brinell
_Desc riptica Piece Nordneee Tenelle Visual Desc ription Mark Spectrol General Wel4
' Conte at Unit #1 LPf2 Reedlag Strength Resulta Analyste Resulte Con formance Resulte Inspection Resulte Interior 31. M'-o* Pipe 6343 Anchor Bolte E"FIHF' 33 o og (p,) -
X OK (t)
Bestraint (4F90) -A-A (i)_
Unit #1 LPf2 si. w -o n e. 8343 348 Rupture
.(.d ok (z) -
k oK (1) -
G) -
l Bestrelat (A490) ._
s j
Unit #1 LPf2
) 51. 94 *-o* Pip 83 6 333 -
Rupture .lg.g OK (2) -
X og (I) -
Restraint (A490) U) ~~ -
Dait #1 LPf2 al. 94 -o .ny, k344 34z Rupture - og (2) -
g og
.sy: A (g) -
(i) -
Restraint (A490) l Unit #1 LPf2 RI. N '-o* Pipe E344 360 Rupture - og (g) .*
)(
Bestraint(A490)
.A.g OK (l) ~
(3) -
! Unit #1 LPf2
, 81. 94 .o n p 325 335
, Rupture -A CK (Z) -
X ok (1) l Bestrelat (A490)
(8) - -
Unit #1 LPf2 al. 9 -o n,. szzs aze Rupture o,c (2) -
g og Restraint (A490) 6 (s) -
(i) -
L l
7*,#2j2;, szzs 338 -
ox (2) -
x ok p
l Rupture - C- (I) -
f8) -
Restraint (A490)
I s l 1
l 03854/
.* TABIJE 1 i
j Bostron-Bergen/Neddeo Natal items Sempled and Reinspection Beru1te SAMPLED ITBE NATERI 1. VERIFICATIOR FfBRICATION VERIFICATION 3 8 /358 Brise11 Ceneral Piece Piece liardnese tenette spectrol Visual Description Description General Weld Mark Beading Strength Beaulte Analysis Boeulte Confo rmance Results faepection Beaulta 3D5 Beaulte Rema ru C ***I Unit #1 LPf2 N *,* te, ,st., 94 -o ripe sfpzs 334 . og y og, (g)
' ' (2) _ _
._ (g _ _
Bestreist (A490)
Unit #1 IM2, El. 94'-o* Pipe Jtff 333 ==
OK (2)
Supture -4 X OK $1)
~
(3) _ -
, Bestraint (A490) .
LP Unit al. w#1. - o,,f2 ,e sus ass -
ox (2) -
x ok (i)
Eupture -F
- 0) .-
Restrelat(A490)
LP Unitf}o*f2 RI. 94 - steam A7.20 317 og (z) x l Generator og (i) -
(3) , -
Vertical Support (A490)
Unit #1 LPf2
- ' si. 94'-o steam AZZo (3) (3) X og Generator -A (1) -
(l) _ -
Vertical Support (1490)
Uatt #1 Inz, i
1 94'-0 st.a. AZZo (3, x l
Cenerator -f (3) ox (1) -
(1) -
Vertical Support (A490) i
' Unit #1 LPf2, s1. 94'-o steam Az2o 323 -
or (2)
Generator -IA X og (f), -
(l) -
Vertical support (1490) l l- .
l.
i 0385d/
5-
i TABLE 1 1 Bostron-Bergen/Neddeo Natal Itees Seapled and Reinspection Beaulte l
l SAMPLED ITWI NATERIAL YERIFICATION
! FABRICAff05 VERIFICATION 4
General as/iss artmell i Fioce > Fioce VI s1 Description hardnese Tene11e spectrol General Desertstion Mark Beedias Strength Resulte Weld
. . Amelyste Resules j C** ** 1'"**
- Conformance Resulte Inspoetten Beaulte NDB Beaulte Bemerke Unit #1 IN 2 i
t a Z
- Lite 51 ***-o* 8' = Azza seeerator 3/s . _ _ _ _- _ . _oK. (z)
Vertical Support 2 .- x ox 0) -
- 0) ___-
(A490) .
Datt #1 IN2,
- - RI. 94'-0* Steam AZZO 3gg Generater OK (2)
' t rtical support 2A .. -
X OK (f ) . (f). -
(A490)
Datt #1 IN2 al. 94'-o st.a. AZZo (3) (3 ) y ces.retor -3 og (f) -
g} -
', Vertical su,xre -
(A490)
Unit #1 I N2 al 94'-o st.a. AZZO 324 .. - ox Generator (2.) -
)( og Vertical hyport -33 0) fl) -
(1490)
Unit #1 IN3.
st. 94'-o* steen A220 Cesare tor (3) (3) X OK (1) -
Vertical Support U) .-
} (a490) i Dait #1 IN3.
st. 94'-o ateen Atto (3)
Generator (3) X OK (f) -
l Vertical Support ,4 0) ., -
(A490)
Unit #1 LPf3.
l s1. 94*-o* st**= AZZo Cenera tor .g 3 2(, -
oK (2) -
X OK a
Vertical Support (l) -
(f) ~
i (A490) e
'! 0385d/
I __ _____ _ _ - _ - -- - --
l -
~
TABLE 1 Boatrom-Deraea/Meddeo IIstal itene sampled and Reinspection Results i SANPLED ITEN
)
MATERIAL'VFRIFICAff05 FABRICATION VERIFICAff05 General Piece BS/let Brinell Description Piece Hardnese Tene11e Visual Descriptf or llerk spectrol General Containment
. Readina strenath Beaulta Analyste Beaults Comformasee Beaulta Weld laspection Resnito 538 Boeulte Ee.orke g,gg pg g,pg3, ratertar
- 1. w -o st.a. Atto .(3) ..
W tolta Generator -IA (3) X or (I L . -
Vertiest support (0 ._.
(A490) ve.it #1 p as, sl 94'-o* st.a. Atto 325 -
oK (2)
Generator -E y og (:) -
(g) , -
Vertical support j (A490)
Unit #1 2 73, st. 94*-o as.a. Att" (3)
Generator 24 (3) x og (I) i Vertical support -
(i) -
(A490) _
Unit #1 LPf3 al. 94'-o stoa. Azzo 357 Generator 3
- og (2) -
X on; Vertical support (e) -
(s) -
4 (A490)
Unit il D F),
si. 94*-o stoa. Atto 3(so -
oK (2) l Generator -JA
)( og (t) -
(8) -
- l Vertical support .
(A490) vatt #1 uf4,
- 1. 94*-o st.a. Azzo (3)
Generator (3) x og (3)
Vertical support (1) -
(A490)
' Unit #1 D f4.
' al. 94'-o , stoa. AZZo (3) (3)
Cene r'.to r X OK (8) -
{g)
Yertical Dupport .A (A490)
~
I O'je5d/
.t
TABLE 1 j
Sostron-Berses/Neddee htel Items Sempted and Reteepection Results s
EAltPLED ITEN llATERIA$ VERIFICATION FABRICATION VERIFICAf!35 l !
35/I58 Brise11
, Seeeral Piece Pisce Visual I Desc ripitee Description lisNeese Tene11e Spectrol General
. Mark Bending Stroaath Beaults Amelysis Beaulte weld Conformance Beaulte Inspection Rosette BDE Seemite Romerke
.. conte 1'amant Unit #1 LPf4.
I Interior 31. 94*-O* Steam 3;4 A2to_ - og (1) -
X og l Anchor Bolte Generator .) (l ) 5 ., (l),__ --
g Vertical Support (4490)
(O. ~~
l _gg g Vertical Support g (A490) l Unit #1 LPf4
- E1. 94 '-0* Steen AZ2D (3) l Generator -2 (3) y og (l) -
(I) -
Vertical Support ~
(A490)
Delt #1 LPf4 E1. 94'-O* Steen AZOO (3) coeerster (3) )( og (l)
Vertteel Support
-24 -
(l) -
(A490) l Unit #1 LPd4
! El. 94*-0* Steen AZoo (3)
Generator ,3 (3) y gg (g; _
(g}_
Vertical Support (A490)
Unit #1 LPf4 El. 94'-o St.es AZN (3) (3) X Cenerator -3A OK (1) -
(I) -
Vertical Support I
(A490) i t
' 03854/
-8 ,
f- .
TABLE 1 Bostrom-Bergen/Neddco Metal Items Sampled and Reinanction Resulte E
SANPLFD ITEN NATERIAL YERIFTCATION FABRICATION YERIFICATION l 88/MN
' Brinell General Piece . Piece Hardness Teneile Spectrol Visual Description Description Mark General Weld Reading Strength Results Analyste Results Conformance Resulte Inspectica Resulte WDR Resulto Remarks Containment Embedmont Plate No shop vertff-Interior on outer Face of 3c.
i^ Annulus Crane well . 44_..
f49 73 kJ/ OK (1) -
(1) -
(1) -
(3) ' -
cation perfo M Structure between 9 a 10 y since there are Support asinuth 263000*
~
Anchor (A36).
Plates Embedmont Plate on outer Face of 3c. No shop _yeriff-
. 84E 70kSi cation oerformed
, Crane sell g, OR (Z) -
(1) -
(f ) -
(8 ) -
since there are at col. 10 asinuth M no exposed shop welds.
- 273030' (A36) .
Containment Support for Interior Unit I reactor Inaccessable for Reactor vessel
~ "" ~ ~ ~ ~
inspection.
Support E 1. 102 *-0"
)( og Ring (ASR8) 4 Containment Embedeent Plate Interior for Loop #1 No shoo veriff-Steam Horizontal AW lu O 6,. . or M) -
(1 ) -
cation performed Generator (# ) - (, ) _
since there are Snubber (A36)
Support at no exposed shop' El. 138' - welds Anchor Plates Embedecin P* ate for Loop (? AE24 No shop veriff.
Horisontal -f i33 M b/ n Q) -
O1 -
III _
[Il _
cation performed Snubber (436) since there are no exposed shop Containment- Anchor Bolte for welds.
S/G r s utal NI ~
I ~
(I ~
j Cenerator Snubber ( A490) -A Support at
. El. 138' -
i Anchor Bolte
j 038si/
, TABLE 1 '
Bostrom-Bergen/Nedeco Metal itema Sampled and Reinspectica Resulte i
, SANPLED ITEN MATERIAL VERIFICA? ION
- FABRICAff05 VERIFICA?!05 BS/Ist Brinell General Piece Piece Hardnese Tensile visual Description Spectrol Gomeral weld Description Mark Beading Strengtb Beaults Analyste Results Comformance Results faspection Beaulte NDE Resulte Senarte I
Anebor Bolte for for loop #1 H24 (j )
(3 ) )( OK ."
+
' 3/0 Morisontal .S (8 ) (f)
Containment A.aebor Bolte for i
Interior for Loop #1 M (3) (3) g 1 Steam 3/C Norisontal -C ..
. . . _ OK (8 )
~
(8) *
Support at '
E1. 138' -
, Anchor Bolte
- Amobor molte for for Loop #1 M (3). (3) X 3/4 N-}risostal . -p OlC (l) -
(l) -
l Saubber (A490)
. Anchor Bolte for p224 3o 7. ex for too, #2 3/G Rorisontal (1) -
X ox (1) -
(1) -
-A Saabber (A490)
Anchor Bolte for for Loop #2 9224 3/9 -
OK (2) ~
X OM (I) ~"
(l) ~
3/G Norisontal .g saubbur ( A490)
Anchor Bolte for for Loop #2 PRA 378 -
o f: (2) -
X og 3/G Noriscatal -C (1) -
(1)
Saubber (A490) t Anchor Bolte for for Loop #2 pzz4 3/0 Morisontal (3) (3) -
X g (1) -
(i) -
9 l Saubber (A490) l 1
! 0385d/
l i
1 i
f TABLE 1 Bostrom-Bergen/Meddco Metal Items Sampled and Reinspection Rendite l
SAMPLED TTfh MATEFTAL YERIFTCATION FABRTCATION YERIFICAff05
- BB/MR Brinell Y1oual General Piece Piece Hardness Tenelle Spectrol General Weld Description Description Mark Reading Strength Results Analysis Results Conformance Resulta Inspection Resulte NDE Results Reserks Containment Horizontal Interior Support Bean - A~ #30 6510/ oK (E) -
K og )( og (g) _
Reactor West side (A?6) 1032 Missile Shield Containment Tangential Beam Al(, l26 G3ASi OK_ (1) -
)( OR Y Og (2) -
~
Interior 5 - 6 (A]6)
Annulus Strvature Radial Beam c g,;, ll3 37 A3; or (2) -
)( og X OK (2) -
at 5 (A36)-
Radial Beam' Al IE3 G I Al** OK I2'I -
X OK X on (t) '- -
at 6 (A36).
Auxiliary Embed Plate in l No exposed shop Building Floor Toc El 115' A309 I3E _(ds ksi olq (2 ) -
(l} -
(1) -
(1) -
weld on this Embedment UR.15-151 piece, (A36)
Plates Embed Plate' in 12 3 GE AS/ oK -
(1) (1) (I) - f0 '"P05'd Sh0P Floor Toe El 115' gM (2. ) - -
weld on this bN.15-151 oject.
(A36)
Embed Plate in No exposed shop Floor Toc El 115' N4 I30 (#I k5i CK (1) -
(I) -
fl) -
(t) - weld on this i
N-R.15-151 Piete.
- (A36)
Embed Plate in No exposed shop vall El 85*
N-R. 151-161 643 /04 Bo Asi ok (2) -
(l}
() -
(1) . weid on this Diece.
. (A36)
Embed Plate in Wall El 85* G R Between C43 /43 7o ggj 'og (2) -
.( g ) .
(l) ,
(l) _
151-16].(A36) 1
! 0385d/
4 TABLE 1 Bostroe-Bergen/Neddeo Metal Items Sampled and Reinspection Results a
~
~
3ANPLED ITEN ' 87ERIAL VERIFTCATION FABRICATION VERIFICATION I I I
BB/NN Brinell .
Visual General Piece Piece' Hardnese Teneile Spectrol General Wold .
l Beecriptica Description Mark Reading Strength Results Analyste Beaults confomance Resulte Inspection Beaulte NDE Resulte Remarke Auxiliary Lower Nelf of Building veritical Support Afd (Gl 81 kSi OK (d - g. OK X og (g) ,,
Jet Beam (A572)
Impingement Structural -
Steel Lower Half of .
(6l
~
Yoritical Support A165 70 kJ/ OK . ( 2.)
X OK X OR )( o JC Beam (A441)
Horizontal No shop welds Support Plat. Fiff /4.5 78 kJ/ OR (2.)
~~
X OK X OK ff-) on this piece.
, (A441)
Auxiliary' Angle Porte .. Angle posts are l Building Supporting A6 ll7 $ 8 kJ/ OK (2. ) --
X O k, X' OK (2) - only members
+
Platform Platform (A36) with shop welds.
' laGWI Angle Poete Angle posts are Supporting 86 Ill . 8 5 #58 OK (2.) X OK )( OR (2.) -
only members Platform (136) with shop welds.
Angle Poets .
Angle posts are Supporting CG ll2. 56 k38 OK ( 2.1
-- y OK y og P2.) -
only members I
Platform (A36) with shop welds.
Angle Posta Angle posts are
!l Supporting D(o 107 53 As! oA (2.) -
X OR y og (2) -
only members Platform (A36) with shop welds.
Angle Poeta gg <
gg ( 7,) - y og y og (2.) - Angle posts are Supporting F6 lll ' only members Platform (A36) with shop welds.
i i Angle Poste Osq . Angle posts are i Supporting 6(a f07 SS ks e, orq ( 7.) - X Og K ( 2.) only members with shop welds.
j Platform (A36)
I i
l 0385.1/
l
- i. -
TABLE 1 Bostrom-Bergen/Neddeo Metal Items Sampled and Reinspection Resulte SANPLED ITIBI MATERIAL YERIFIC LTION FABRfCATION YERIFICATTON 8
BB/IOt Brinell Visual General Piece Piece Hardness Tenelle Spectrol General Veld Description Description Mark Reeding Strength Resulte Analysis Resulte Conformance Resulte Inspection Resulte NDE Resulte Remarks 4
Puel Ceiling No exposed Handling hbedeent Plates IE6 03 %" oK (M -- (l) - I3) " (f shoo weld on Building El 115 this piece, hbedmont T-Y.15-121 -
Plates (A441)-
Ceiling . (g) No exposed-Embedeout Plates HLF i38 (< B F5s OK (7-) -- (1) - III -
shop weld on El 115' A this piece.
T-Y.15-121 (A441)
Ceiling No exposed Embedaent Plates flI7
- E9 (OIASI CN I Z-) 1 (I) --
(l) -. (l) - shop weld on El 115* ~
this piece.
T-Y.15-121 (A441)
Ceiling . No exposed hbedmont Plates WIS7 13 0 (sSA5/ OK ( Z.) (g) (g) shop weld on i
El 115' (p _,
this piece.
- T-Y.15-121 (A441)
{
Ceiling No exoosed i Embedmont Plates El 115' Ac-f57 12.9 (a4 ksi og ( z) -
() _
gg _
g ._
shop weld on this piece.
T-Y.15-121 1
(A441) -
Turbine Horizontal Beam Full penetration
- Building E1 103*-6*. F-G D49 16 7 79Fs/ CK (4) ~
X OK X OK )( OR weld.
CCW Heat and 143,(A572)
I Exchanger Barrier l .
! l Y
I 03asd/
t TABLE 1 I Ecstrom-Bergen/Neddco Metal Items Sampled and Reinspection Results i
1 i FABRICAff0N YF1IFICATION SANPIEJ ITEN MATERTAL YERIFICATION BB/let Brinell Visual General Piece Piece Hardnese Tensile Spectrol General . Weld .
Description Description Mark Reading Strength Results Analysis Results Conformance Beaults Inspection Resulta NDE Results Remarks ~
Bulk 1"x2-1/4*r2-1/4" 6* 153 75 AS/ os (2 ) -
(f ) -
(f ) -
(l ) -
Current 1{ in QC
- Hold Material: Plate (A441) 793 area. To-be l Plates .
installed in a Unit 2 pipe rupture restraint.
d- N89 8 E AJi OK ( 2- ) -
(l) ~
II) - llI -
Current 1{ in 1"u2-1/4"x2-1/4" QC " Hold j Plate (A441) 793 area. To be I installed in .
- a Unit 2 pipe n pture I'
restraint.
4- I$4 78 ASE OA IEI ~
b)
~
(I! ~
(I
- Currently in 1"x2-1/4"x2-1/4" QC " Hold" Plate (A441) 793 area. To be installed in a Unit 2 pipe rupture re strair.t .
t Currently tu Buls vT3x6 6- 142. yo g3/ g (g) - (i) -
(i)
(f ) -
QC " Hold" Materials (A441) 793 area. To be Structural installed in Shapes Unit 2 pipe rupture restraint 8-2BR.
4 OJ85d/
TABLE 1 Notes (1) Test / inspection is not applicable to this item.
(2) Test / inspection is not necessary for this item. ,
(3) Test / inspection is in-progress.
(4) NDE records, from an independent testing lab, indicate that the shop
.welds (BB/MM welds) are acceptable. These records are on file.
(5) liardness readings were obtained using an Equitip testing machine.
(6) "I" indicates that' the test / inspection was performed for this item.
I .
l
~
l 0384d/
l L .