|
---|
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:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20236U6921987-11-20020 November 1987 Telex from San Luis Obispo California Mothers for Peace Re Facilities ML20236C1201987-10-20020 October 1987 Forwards Request for Stay Filed by Sierra Club in Proceeding Re NRC Issuance of Amends 8 & 6 to Licenses DPR-80 & DPR-82,respectively.Requests Commission Act on Request by 871026 ML20235K7941987-10-0202 October 1987 Informs of Change of Address for Receiving All Matls Related to Facility.New Address Listed.Served on 871002 ML20235F2561987-09-24024 September 1987 Forwards Request for Stay & Notice of Appeal of Licensing Board 870911 Initial Decision,Authorizing License Amends & 870902 Order of Board Denying Sierra Club Motion to Admit Contention & Request for Preparation of Eis.W/O Encl ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20237G9911987-07-28028 July 1987 Comments Supporting Onsite Storage & Reracking Until Federal Repository for Storage of All Spent Fuel Built.Support of Util & Facility Operations Discussed ML20236K7881987-07-0202 July 1987 Appeals Denial of FOIA Request for Interview Tapes Re SER of Operation of Plant ML20235G8501987-06-15015 June 1987 Appeals Denial of FOIA Request for Documents Re Plant Listed in App E.W/O App ML20215B1431987-02-25025 February 1987 FOIA Request for Listed Documents Re Mgt of Facility QA & QC Personnel ML20213A3971986-11-30030 November 1986 Summarizes ACRS Subcommittee on Extreme External Phenomena 861120 Meeting Re Facility long-term Seismic Program.Studies Necessary & Conducted in Excellent Manner ML20214P8771986-09-16016 September 1986 Submits Addl Corrections to 860822 Preliminary Conference Transcript.Requests That Response Remain Open Until 860919 in Order That Items Be Accurately Researched & Corrected. W/Certificate of Svc ML20212L1781986-08-18018 August 1986 Forwards Rept on Efforts to Resolve Sierra Club Contention (I)(A) ML20207H7661986-06-25025 June 1986 Supports San Luis Obispo Mothers for Peace & Sierra Club Request for Stay of Issuance of Amends 8 & 6 to Licenses DPR-80 & DPR-82,respectively.Problems Associated W/No Significant Hazards Determination Noted ML20214T6541986-05-28028 May 1986 Appeals Denial of FOIA Request for Ofc of Inspector & Auditor Rept & Related Documents Re Allegations That NRC Responded Improperly to Allegations of Whistleblowers at Plant.Response Requested within 20 Working Days ML20214T7651986-03-0404 March 1986 FOIA Request for Documents Re Ofc of Inspector & Auditor Investigation & Audit of Charges That NRC Improperly Responded to Allegations of Whistleblowers at Plant ML20210G9101986-01-27027 January 1986 Undated FOIA Request for Transcript of Closed Commission 811119 Meeting to Discuss Suspension of Diablo Canyon Unit 1 Low Power OL ML20141N3161986-01-14014 January 1986 FOIA Request for R Jackson to R Vollmer Re Diablo Canyon Hearing Reopening & San Onofre Review Status ML20138Q8561985-11-20020 November 1985 FOIA Request for Documents Re Ofc of Inspector & Auditor Investigation Into Charges That NRC Responded Improperly to Allegations by Whistleblowers at Facility ML20133G9571985-08-20020 August 1985 FOIA Request for Documents Re Ofc of Inspector & Auditor Charges That NRC Responded Improperly to Allegations of Possible QA & Safety Violations by Whistleblowers at Plant ML20198M9631985-06-17017 June 1985 Forwards Allegations of Safety Violations of Nuclear Regulatory Law or Westinghouse QA Requirements.Investigation Requested.Related Info Encl ML20133H5871985-05-0808 May 1985 FOIA Request for Documents Re Plant,Including All Contacts Between DOE Task Force on Commercial Nuclear Power,White House Cabinet Council Working Group & NRC Concerning OL ML20128Q6531985-05-0808 May 1985 FOIA Request for Three Categories of Documents Re Facilities ML20128P8031985-04-0808 April 1985 FOIA Request for Access to or Records Re Potential Environ Impact Associated W/Fuel Loading &/Or Low Power Testing at Diablo Canyon & AEOD Sept 1980 Rept on Browns Ferry Interim Equipment to Detect Water in Discharge ML20126J0361985-03-26026 March 1985 Ack Receipt of 850325 Telegram Re Followup Interview of Clients for Pending Allegations.Finalization of Interview Schedules Requested.Second Witness Name Should Be Deleted If Telegram Publicly Available ML20127F1741985-02-0101 February 1985 FOIA Request for All Records & Info Re Vendor Insp Branch 840229 Rept 99900840/83-01 at Cardinal Industrial Products Corp That Mention Diablo Canyon ML20107K7771984-11-28028 November 1984 Appeals Denial of FOIA Request for All Transcripts from Commission June,Jul & Aug 1984 Meetings Re Issuance of Full Power License for Facility ML20215L7951984-11-15015 November 1984 Forwards Amended Mcdermott & O'Neill Petition Re Plant,Per 10CFR2.206.Exhibits 7-18,consisting of Affidavits from 12 Witnesses,Being Filed W/Nrc to Avoid Compromising Ongoing Ofc of Investigations Investigation.W/O Encl ML20133Q2971984-11-0505 November 1984 Appeals Denial of FOIA Request for Transcripts of Commission Meetings Held During June,Jul & Aug 1984 Re Effects of Earthquakes at facility,SECY-84-70 & SECY-84-291 & Commission Final Order CLI-84-12 ML20107C4631984-11-0101 November 1984 Forwards Mc Thompson,Tm Devine & Lockert Affidavits Representing Portion of Results from 841009-30 Investigative Trip.Commission Has Adopted Adversary Position W/Respect to Public Since 840817 Stay ML20107H7671984-10-19019 October 1984 FOIA Request for Documents Re Commission Meetings Held During June,Jul & Aug 1984 on Complicating Effects of Earthquakes on Emergency Preparedness ML20107H0161984-10-15015 October 1984 FOIA Request for Documents Re Facility,Including Transcripts of Meetings Concerning Issuance of Unit 1 Full Power OL ML20107F9121984-10-0909 October 1984 FOIA Request for Transcripts of Closed Commission Meetings Held During June,Jul & Aug 1984 Re Complicating Effects of earthquakes,SECY-84-70,SECY-84-291 & Drafts of Final Order CLI-84-12 & Related Documents ML20107J4551984-10-0404 October 1984 FOIA Request for Documents on Jul 1984 SER Re Operation of Facilities ML20107J8011984-09-13013 September 1984 FOIA Request for Documents Re 840612 Congressional Briefing on Facility ML20129A3601984-09-13013 September 1984 FOIA Request for Documents Generated in Connection W/Sser 22 (NUREG-0675) Re Operation of Facilities Which Provided Further Findings on Whistleblower Charges ML20117B7041984-09-13013 September 1984 FOIA Request for Documents Re Sser 26 (NUREG-0675) Concerning Operation of Diablo Canyon Plant ML20107K5221984-09-13013 September 1984 FOIA Request for Documents Re Ofc of Inspector & Auditor Rept by R Smith on Allegations of Staff Misconduct at Facility ML20213F0181984-09-0404 September 1984 Alleges That NRC Handling of Allegations Has Shifted Burden of Proof to Allegers & Posed Threat to Anonymity.Nrc Posturing Also Alleged.Recommendations for Improved Handling & Relationship Between NRC & Whistleblowers Given ML20096H4441984-09-0101 September 1984 Suggests That Yin Be Assigned as Technical Liaison to Work W/R Meeks on Investigation.Team Could Help Regain Respect & Perform Definitive Exhaustive Investigation No One Could Challenge ML20117M9621984-08-0101 August 1984 FOIA Request for Probabilistic Seismic Safety Assessment of Diablo Canyon Nuclear Power Plant & Amend 52 to FSAR ML20093N8071984-07-31031 July 1984 Forwards Suppl Supporting T O'Neill 840727 Petition Under 10CFR2.206 on Behalf of J Mcdermott & T O'Neill.Also Expands Original Request for Retraining ML20093K0901984-07-29029 July 1984 Forwards Attachment 1 to T O'Neill 840727 Petition,Omitted from Original Submittal Due to Administrative Error. Affidavits in Support of Petition Will Be Executed on 840730 ML20093K1821984-07-27027 July 1984 Submits Petition to Defer Any Further Licensing Decisions Until Effects Neutralized from Onsite Harassment & Retaliation That Have Intensified Since 840413 Low Power Testing Decision ML20090H7461984-07-25025 July 1984 Withdraws Allegations Against NRC Staff as Summarized in Rept of Interview W/Ofc of Inspector & Auditor Atty R Smith. Methodology for Investiation Obviously Designed to Predetermine Results ML20093G5751984-07-23023 July 1984 Clarifies & Suppls 840716 Petition by Requesting Public Participation in 840726 Plant Tour,Nrc Public Rept on Postponement of Util Compliance & Naemark Comments on NSC Audit ML20093E5021984-07-16016 July 1984 Petitions Commission to Take Six Listed Minimum Steps Legally Necessary to Assure Public Safety Before Issuance of Ol.Petition Submitted,Per 10CFR2.206 ML20090A8451984-07-11011 July 1984 Forwards Affidavit of T Devine Notifying of Resignation of I Yin from Review Team Overseeing Plant Readiness for Commercial Operation,As Suppl to 840503 Petition Under 10CFR2.206 ML20092N1441984-06-29029 June 1984 Extends Time Limit for Relief within 840503 Petition Filed Per 10CFR2.206 Until Date When Commission Schedules Licensing Vote on Commercial Operations.Deadline Extended Due to Large Vol of New Evidence ML20092G7121984-06-21021 June 1984 Forwards Summary of 17 Addl Witness Statements Gathered in Support of 840503 10CFR2.206 Petition to Defer Further Licensing Decisions Until Completion of Listed Tasks ML20140C6471984-06-15015 June 1984 Extends Deadline for Commission Response to Mothers for Peace 840503 Petition Per 10CFR2.206 Until 840629 1987-09-24
[Table view] |
Text
. . _. __. - - _ . . _ _ _ _ . , _ ___ _
GOVERNMENT ACCOUNTABILITY PROJECT i institute for Policy Studies 00CKETED 1901 Que Street. N.W.. Woshington. D.C. 20009 um; (202)234-9382
- b4 k M 1SE5 1984 Nunzio J. Palladino, Chairman ,e.---c,-c-Victor Gilinsky, Commissioner Thomas Roberts, Commissioner -
. James Asselstine, Commissioner Frederick Berrthal, Commissioner U.S. Nuclear Regulatory Commission 1717 H Street, N.W.
- Washington, D.C. 20555 Re
- Diablo Canyon Nuclear Power Plant, Units 1 and 2 Docket Numbers 50-275 and 50-323
Dear Commissioners:
This letter and enclosed affidavits is to provide the Commission with notice of a potentially serious discrepancy at the Diablo Canyon nuclear power plant, Unit I. The issue was not discussed by the staff in its recent commission briefings but if correct must be addressed prior to criticality. The alleged problem concerns violations of minimum wall thickness on reactor coolant system piping. More specifically, the alleged deficiency exists adjacent to weld No. WIB-RC-2-16 on the safety injection accumulator (or core flood tank) line. This line ties into the, line between the reactor coolant pump and the reactor vessel.
The significance of the issue is self-evident from a review of the public record. The. licensee's five month delay from December 1982-May 1983 in reporting similar violations on an adjacent. weld led to a citation, due to the necessity for " remedial action or corrective measures to prevent the existence or development of an unsafe condition." Indeed, the condition was so significant that-it had to be . reported in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. See Board Notification 50-275/
83-83 (June 24, 1983). In theory, this serious condition was resolved through a corrective action plan approved by NRC Region V inspector Dennis Kirsch. See IE. Report 50-275/83-26 (August 5, 1983).
' GAP's introduction to the issue was a March 21, 1984 affidavit:
from an anonymous witness who disclosed problems with what turned out to be weld RC-2-16,on pages 5 and 6 of the statement. The
. affidavit. otiginally' was submitted to the Commission as Attachment- 12 to a March 23, 1984 supplemental petition under'10 C.F.R. 2.206.
The affidavit is . enclosed as Exhibit .l.
On the April 11,.1984 plant tour the witness'ponfirmed to NRC inspector Kirsch and GAP' investigator Richard Parks that the problems.
with weld RC-2-16 were still uncorrected. See'. Mr. Parks' April 17,.1984 affidavit, at pp.1-3, enclosed at. Exhibit 2, quoting inspector Kirsch's " Problem Description." The conditions. confirmed by Mr. Kirsch's Problem. Description obviously violate ASME Section III L and are symptomatic of minimum wall thickness violations on the piping. f, 5404260498 540425 F' PDR ADOCM 05000275
. cG>~ _
R GDR
f d
The significance of the findings from the plant tour is clear.
Initially, under the regulatory requirements quoted in IE Reports 83-20 and 83-26, the condition must be corrected due to its extreme safety significance. As pointed out in IE Report 83-20, at p. 5, the minimum wall thickness violations "if left uncorrected could have resulted in degradation or loss of integrity of the reactor coolant pressure boundary. " Quite possibly, they still could.
Second, on April 13 Mr. Martin directly misinformed the Commission by concluding that the plant tour had not uncovered any code violations. Other examples that demonstrate the f alse nature of his statement also are discussed in Exhibit 2.
Third, the licensee's 1983 remedial program on this issue --
approved by the staff, including Mr. Kirsch -- failed to correct the full extent of discrepancies. The licensee was on notice, since the anonymous witness had identified weld RC-2-16 on-site over a year ago, in March or April 1983. (Exhibit 1, at p. 5) .
Counsel planned to raise this issue next week as part of a new petition under 10 C.F.R. 2.206 for corrective action prior to commercial operation of Diablo Canyon. Mr. Parks' ongoing review of previous Region V inspection reports, however, revealed that the issue is so urgent it must be disclosed immediately.
4 Mr. Parks and counsel are at your disposal to help expeditiously resolve d1is potentially serious hazard.
Respectfully submitted,
. . - M__
Thomas Devine Counsel '
Mothers for Peace ;
3 Attachments y , , , . - --
Exhibit 1 AFFIDAVIT Ny name is I am submitting this affidavit freely
~
and voluntarily, without iny threats, inducements or coercion, to sir. Thomas Devine, who has identified himself to me as the legal director of the Government Accountability Project. Dam submitting this statement to evidence my concern about the effects of quality assurance violations during 1983 by the HP Foley Corporation that
?
Oth:1., occurred at the Diablo Canyon nuclear power plant.
i was employed at Diablo Canyon for a period of approximately 4
four montns, (January 1983 until April 1983), as a Civil Quality Control Inspector. As a Civil QC Inspector I routinely' inspected welding and perfonned non-destructive testing of welds performed on Seismic Category I structures in both the Fuel Handling Building and inside containment. '
Even though I have over thirteen years welding experience and am stvetutAL. 9rgggyo a certified & hefpipe welder I was only qualified to a Level I inspector. In accordance with the Quality Assurance / Control procedures that I mad as part of g indoctrination, I was not allowed to accept work based on g inspection. The procedures required a Level II (senior) Inspector to sign for acceptance. I complained on nunperous occasions about the fact that I was inspecting welds that I was not certified to inspect. The interin response was to have a Level II inspector cosign g work after I turned in the inspection altnough he had not looked at the welds. This illustrates a widespread problem
. of falsified inspection records. The final response of supervision was to upgrade g certification to that of a Level II inspector.
' .~.;
, o. ,
2-
- 40st of the weld inspectors did not have nty background in the trade. In fact, there only were isolated instances where the inspector knew how to weld at all. That can compromise the quality of inspections; it can't all be taught by books and pictures. You have to be able to understand the process. From my own observations, up to 30% of the weld inspectors weren't qualified. I base that conclusion on the poor quality of the work they accepted. This included welds where the ceAPLEYEW i slag hadn't beenVehipped off, making it impossible to have actually visually checked the weld quality. In other cases they could not l translate the blueprints. In still other instances the unqualified j inspectors erroneously rejected acceptable work, and on the basis of unexplained vague terms such as " bad weld profile." This created a backlash from the production department.
l l
On my shift, there were only five weld inspectors with Level II stamps. In my own case at least, however, that was bogus because they didn't nave any papemork. I know, because I would have been involved I l
with filling it out. ;
I When I first hired in with HP Foley, the Manager, V. Tennyson, had )
waffK 1 ne spend the first t r 3. - 2 ,; reading the relevant procedures. l I was then placed in the weld test booth. My responsibilities were to certify welders by performing various welding procedures in various positions and fit ups.
I took ey duties seriously, even though by procedure I wasn't certified to certify other welders. 'On the average I " looked-out" --
or flunked before the exam even reached the stage of a destructive
~
-_ - - . . _ ,. ,,._..-- - .-- , - . , .-,y--.,,.p.. 7,,, y... . .,.,.-,.m . -w, 7 ,,- - .- ,..,m.. ..,
test -- over fifty percent of the welders attempting to qualify, on at least one cecasion. The flaws in their work were obvious and severe.
They included excessive peeving, which involves beating up the weld trying to get the o'ff; massive undercuts and failure to follow the steps of the welding procedure they supposedly were being tested on. In some cases, I " looked-out" welders because they took the plates out of position to get a better angle for the weld.
Even the welders who passed did not have unique stamps required to identify ar.d trace their work, as required by the American Welding Society (AWS) code. A welder cannot receive electrodes to do the work, without his personal stag. Instead, management instructed them to borrow one from.the fabrication shop. I personally didn't tolerate this practice, and wouldn't let them go into the field or accept work ,
until they obtained their own stamp. But the abuse went on all the time.
When I told management that welders wanted to weld without stamps, the response was, "we don't have any."
The procedure prevented the welders from taking the requalification test until they had been adequately trained in the welding process.
However, management routinely allowed them to take the test daily until they passed.
old In some instancejlI flunked the same individual five times l
running.
To me this practice constituted nothing more than on-theljob train-ing in the weld test booth under ideal conditions. After about a month of complaining about this practice I finally convinced sqy supervisors j i
4-to reassign me. I couldn't handle compromising my personal beliefs for the benefit of supplying welders that I felt were not qualified. I believed a reassignment to the field would no longer require me to conpromise what I believed in. I was wrong.
Even though the QC Inspectors were supposed to participate in a continuing training program, I can only recall one instance where the inspectors were taken out of the field for a training seminar. That meeting was a fiasco, which suggests to me that personnel still may be reading the blueprints backwards. Round the end of January 1983 all Foley Inspectors attended a meeting to discuss the " interpretation of the Fuel Handling Building blueprints" This meeting was to clear up trie confusion over whether they were to be viewed from the "inside looking out" or the "outside looking in." Nothing was resolved. In fact management conducting the meeting couldn't agree on how to view the -
blueprints. The inspectors were finally ordered back to work while the managers resolved the issue. I presume the confusion continued in the field, since training was not reconvened to resolve the question.
i Another practice that greatly disturbed me was lack of material 4
traceability. Before a piece of metal was cut from the steel plate in F
the TQrbine Building Fab shop, the original heat number from the .
steel plate should have been stamped onto the piece cut from it. This ~
c.optser is important.. Without thisYnumber on the material, the QC inspectors ceu!d not determine whether or not the steel had the metallurgical properties for the application on which it was used. Just aspect
^
of the significance is that welding by an improperly chosen process i
e r ~- , -p r -e -r-w - , - +
--ww e- e, e e--'wr r-w--r m,r-o-w,,w- --,u,-m -.-w - - - - ow, - - -
w---wo-----,r-~----- -
- - - . - . . . - .. . - .. _. ~ = . _ _ _ . . __. .-.
, l
-5 could result in < degrading the strength of the steel.
In practice, however, traceability was lost after the material was received. The heat numbers were not consistently transferred. As a result, there were heat numbers on the material without supporting documentation to verify accuracy.
In the field traceability was further lost, due to modifications on flatbar structural steel. Traceability was lost for the steel in the process. In the fuel handling building.
heat numbers were even swapped. This occurred for knee braces on columns providing seismic support to hold up the walls. In fact, in that case r
the traceability records are backwards. The :auth side heat numbers apply to their countenarts on the north wall. Even though I and others 1
identified this problem M " ~ .... no satisfactory solution was '
ever arrived at. Mr. Tennyson's efforts appeared half-hearted in that the "up to date" heat log we were supplied with had no control measures assigned to it. It would have been a simple task for anyone to alter this log. 2.15tustY Mr. Tennyson also knew that some of the steel being 4
on the plant was foreign steely -4c:kmeur. I>ecause a fellow worker showed me proof of this practice. The use of foreign steel would have violated a company agreement to not use any in the facility.
Arount March 1983, I was assigned to inspect the addition of I-beams and clips to one of the Reactor Coolant Pumps. These additions were -
necessary to provide seismic support for the pump. letile I was inspect-
' ing the additions I noticed a stainless steel T-section of pfpe, under the Reactor Coolant pump on the 125 foot elevation, that had a 4 inch linear undercut. Per the procedures in use at the time, there could be g-----'
no undercut on that piping. I brought this to the attention of my supervisor immediately. His response was " mind your own business....
it's Pullman's responsibility." This didn't wash with me, so I informed a PG&E employee whose responsibility was to document problems.
, i[M% PG&E perfonned some Ultra-Sonic Testing of the pipe and found the wall thickness to be insufficient in the areas of the weld in question.
However they decided not to fix it, perhaps because the weld was in-accessible from the outside. When I left in April 1983 the weld had never been repaired.
Prior to my leaving Diablo Canyon. I discovered that the " Guided-BGMo Sevel Test Machine" did not satis.fy AWS requirements with respect to operating tolerances between " shoe and die" in the hydraulic jack. The rollers were also extremely sloppy. To some this may not seem significant; However, if this machine is not set-up properly it could artificially qualify " bad" weld test coupons. This machine was apparently wom out. I identified this to my supervisors and was told to " quit being picky."
The final insult to injury occurred during ny exposure to the l
" Quick Fix" program. After I would inspect a hanger, strut, or other item k would explain to a " Quick Fix Engineer" what I felt needed to be done. Ususally within half an hour he would be back with the requisite ;
1 paperwork for the " quick-fix". Engineers approved such significant modifications as the addition of T bars and changes that effe,Stively redesigned the wall plates. The expediency in which this paperwork ap- '
peered assured me that it could not have been reviewed by QA or had any I
serious engineering analysis.
l l
7- ;
Also, the professional codes that represent the legal basis for our conclusions frequently were not available. I attempted to research them, but routissely these documents were " lost" when I looked for them In some cases I could not even find up-to-date copies of the
" quality control procedures." When quizzed about their locations, my
. supervisors would reply that they were amund somewhere and would promise to locate them for me. In the interim I was instructed to go
. ie4 Mav cAsrf back to work.VThey never found the documents for me. It was obvious to me they wanted me to know just enough to do g job and not enough to do it well.
- Th:fe'p=: ;;; I M finally led ee'=to resig8oin April 1983. I believe in quality of a man's work. Over the last 13 years I have worked as a welder in oil fields, ;;be' eM --M..t-M4aeays, heavy equipment mpair and structural steel femmene-
. 2. stH*nc l $3:^J ?%A.t e !,_ ' --te, Of ^2:2 j:bs,Vfmm a quality perspective Diablo Canyon t
-(ig6s;..t; 10 St RE 5 hm.. m sAccrec ;f W lhe.
I have read the above 7 page statement and it is true, accurate and complete to the best of g knowledge and belief.
e 9
w.-, -- - .--,,,s-wm...,,a-. ,.,,,,,a., -
, , -,a --_,,,.,y~,-n- - , - an,--- , , - - - , - - , , ., - - - , , , _ , - . .,,,..-_,,_w,-
STATE OF CALIFORNIA )
) ss.
COUNTY OF SAN LUIS OBIPSO )
On March 21, 1984, before me, the undersigned, a Notary Public in and for said Stara, personally appeared a or proved to me by satisfactory evidence to be the person whose name is subscribed to the within instrument, and acknowledged to me that he executed the same.
WITNESS my hand and official seal.
SUSAM HAWKF -
'N
,, a Public in and for said mnesw.Omca w
- SAN t UW OSSPO COUNTY # l I W M E *5_4 -
//
l l
l l
l
.. - _ _ ~ _ _ _ - . .- . - . -- .. _ --- .-. . -- ._
4 Exhibit 2 My name is Richard D. Parks. I am submitting this affadavit to document the discrepant conditions identified, and corresponding violations of the applicable codes as a result of the plant tour conducted on April II,1984 with D. Kirsch and G. Hernandez of Region V, United States Nuclear Regulatory Commission (NRC) at the Diablo Canyon Nuclear Power Plant.
I and three witnesses accompanied the NRC to provide "handswon" examples of non-compliance with regulations, specifications and codes that form the basic cornerstone of a comprehensive Quality Assurance / Quality Control program.
Each example identified to the NRC was subsequently " tagged" for identification and a " report sheet" was filled out by the NRC. The " problem description i' is a quote from the report sheet. The examples identified that violated applicable codes are discussed as fo11ows:
ITEM #1. Tag #2: Elevation 116, Unit 1 Reactor Building. Line Designation NO.S2-254-10, in the area of Pressurizer and Reactor Coola'nt Pump 1-2 Problem
Description:
Wald attaching Safety Injection Accumulator line to nozzle of the cold leg line (NO.S2-254-10). On the side facing Reactor Coolant Pump (RCP) is a grinding gouge in the Mpe at the '
pipe-weld interface approximately 3/8 inches long,1/8 inch at A
- W 2
widest point and 1/16 inch deep (dimensions as visually determined by l NRC Inspector - no measurements taken). Additionally, there appears to be a slight amount of undercut at two locations. The undercut is approximately 5/8 inches on the weld side facing the RCP and appro:ci-mately 1 inch at 120 from the side away from the RCP.
. ;..y Code Violation: American Society of Mechanical Engir.eers (ASME)
Section III, " Rules for Construction of Nuclear Power Plant Components - 1977 edition, Division I General Requirements, Subsection NB, " Class 1 Components", para NB-4424 " Sus faces of Welds",
"As-welded surfaces are permitted, and for piping the appropriate stress indices given in Table NB-3683.2-1 shall be applied. However, the surface of welds shall be sufficiently free from coarse ripples, grooves, overlaps, and abrupt ridges and va11eys to meet (a) through (f) below:
(a)...
(b) . . .
(c) Undercuts shall not exceed 1/32 inch (0.8mm) and shall not encroach on the required section thickness.
(d)...
A
RP 3.
(e)...
(f)If the surface of the weld requires grinding to meet the above criteria, care shall be taken to avoid reducing the weld or base metal below the required thickness."
The discrepant condition identified by the witness violates the code requirements with respect to being " free from coarse ripptes, grooves, overlaps, and abrupt ridges and valleys to meet (c) and (f)."
ITEM #2. Tag #4: Unit 2 Reactor Building, Elevation 115, Support 97-3R in vicinity of RCP 2-3.
Problem
Description:
" Excessive overweld has caused excessive shrinkage of SS line. This was supposed to be a fuit penetration weld with fillet'
- cap and is as specified. The overwelding can damage the pipe because calculations don't account for residual stresses caused by such overwelding."
Code Violation: United States of America Standard (USAS) B31.7-1969
" Code for Pressure Piping - Nuclear Power Piping" (note: this standard now is known as ANSI-B31.7), foreword " FABRICATION REQUIREMENTS .
AND THEIR CORRELATION WITH DESIGN", page XVI paragraph 5.
"Even hanger attachment details are covered. For Class I piping, complete penetration welds are required. The designer must consider all stresses in the attachment as well as their effect on the pressure
-69
a 4.
retaining part. "
The welds in question do net conform to the stated intent of the
" Nuclear Power Piping" code with respect to the residual stresses induced by the overwelding. It is the concern of this particular anon-ymous witness that these residual stresses should have been but were not a factor in the design calculations. '
- ITEM #3, Tag #5: Unit 2 Reactor Building, large restraint wall attachment (around surge line), beneath Unit 2 Pressurizer.
Problem
Description:
"Shopwelding is supposed to conform to AWS Dl .1 standards. The inner welds are excessively rough and of such a profile that they would not conform to AWS DI.1 The welds are ragged."
Code Violation: American Welding Society (AWS) Structural Welding Code - Steel, paragraph 8.15 " Quality of Welds", subparagraph 8.15.1 "Vis ual Ins pe ction". "All welds shall be visually inspected. A weld shall be acceptable by visual inspection if it shows that 8.15.1.1 -The weld has no cracks
- 8.15.1.2 Thorough fusion exists between adjacent layers of weld metal and between weld metal and base metal 1
. . , , h
5.
8.15.1.3 All craters are filled to the full cross section of the weld
- 8.15.1.4 Weld profiles are in accordance with (para.) 3.6
[,w eld profile] "
The weld in question does not conform to the requirements specified in paragraph 3.6 [, weld profiles) or the evident thorough. fusion requirements as stated in 8.15.1.2 ITEM #4, Tag #6: Unit 2 Auxiliary Building, area GW, elevation 115, line No. 2-S2-265-8 (Containment Spray Discharge Pipe - 4 lug attachments between S and T line.)
Item
Description:
" Lug attachments are called out to be 1/2 inch fillet welds on three sides. Actual size is 7/16 inch fillet or less."
Problem
Description:
" Actual size is alleged to be less than or equal to 7/16 inch which is 1/16 inch less than required. The excessive welding used in the design of the lugs attachment welds, when welded to Schedule 10 stainless thin wall pipe, has caused excessive shrinkage.
The excessive shrinkage causes residual stresses in the pipe which has not been account.ed for in the design or stress analysis. The position of the clamp is such that there is a torsional force applied to 90
T 6.
the lugs, because the clamp cannot contact the wall of the pipe due to the shrinkage. This torsional force is not accounted for in the design and compromises the pipe integrity."
Code Violation: Refer to " Code Violation" discussion in " ITEM #2, Tag #4".
The welds in question do not conform to the stated intent of the
" Nuclear Power Piping" code with respect to the residual stresses induced by the welding or the torsional icrce applied to the lugs due to excessive shrinkage. It is the concern of this particular anonymous witness that these stresses should have been but were not a factor in the design calculations .
ITEM #5, Tag #7: Unit 2, Auxiliary Building, Area 2H, support 413-131R around CCW line.
Problem
Description:
"Eight lug attachment welds are required to be full penetration welds on three sides. Actual weld is not a full pene-tration weld, but is, instead a fillet weld, contrary to the design." !
Code Violation: -American Welding Society (AWS) - A2.4 - 79
" Symbols for Welding and Non-Destructive Testing," paragraph 9. 0
" Groove Welds," subparagraph 9.2.2 " Complete Joint Penetration I
.. 1 R e quire d . " "When no depth of groove preparation or effective l
i l
l
i throat is shown on the welding symbol for single-groove and symmetrical double-groove welds, complete joint penetration is required."
l 3 $ @ns
} \ Symbol provided on " Detail" ,
for weld (s) in question.
PG and E has stated in their letter, DCL-84-040, "The"Neld symbols used at Diablo Canyon are consistent with the standards specified in AWS. . . " and in an Interoffice Memorandum (file no. 930, 146.20, CA2) dated October 25, 1983 that "all pipe support as-builts issued by General Construction after October 15, 1983 should have g1 weld symbols in conformance with AWS A2.4."
The welds in question were incorrectly performed because of lack of proper interpretation of the weld symbol utilized on the design drawing.
It is the concern of this particular anonymous witness that this discrepancy provided an example of code compliance violation due to a lack of intimate knowledge with AWS A2.4. These particular welds had been inspected and accepted by Pullman Quality Control and PG and E
~
Quality Control prior to the discrepancy being identified by a Pre-Inspection Engineer.
q e
l I have read the above eight page statement. I have based the information contained therein either on personal knowledge or by reviewing the relevant information with the particular witness involved. This statement is true, correct and complete to the best of my knowledge and belief.
I declare under penalty of perjury that the foregoing is true and correct, and that the same was executed this 17th day of Ap'rIi",1984 at San Inis Obispo, California.
4- . 4 RIQiARD D. PARKS, clarant STATE OF CALIFORNIA )
) ss.
COUNIY OF SAN 1RIS OBISPO )
On April 17, 1984, before me, the tmdersigned, a Notary Public in for said State, personally appeared RIGIARD D. PARKS, personally known to me and proved to me on the basis of satisfactory evidence to be the person whose name is subscribed to the within instrunent, and that he executed the same.
WITNESS my hand and official seal.
i .
... _ w - - - -- , -
l M@ ; t.! P !TR
. c.n' ; < r".4ac . cAu cR'" '
b ha, m Notary Publ2 in and for b
y; ,,7 '
Jn: MS OWo COUNW >
said CoLEty and State My Ces.m Enirp Mo/ 9,1986 (
, .