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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 OAS AND ELECTR,IC C O M PANY EOWb l 77 BEALE STREET . SAN FRANCISCO, CAUFORNI A 94106 . (4151781 4211
- TWX 910 372 6587 J. O. SCHUYLER
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April 11, 1984 PGandE Letter No.: DCL-84-140 Mr. John B. Martin, Regional Administrator U. S. Nuclear Regulatory Commission, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-76 Docket No. 50-323 Diablo Canyon Units 1 and 2
- Revision to IEIR 83-37 and 83-25 -- Notice of Violation l
Dear Mr. Martin:
! NRC Inspe.ction Report 50-275/83-37 and 50-323/83-25, dated February 29, 1984, included a notice for a Severity Level IV violation. PGandE responded to this notice on March 29, 1984 (PGandE Letter No. DCL-84-124). This response supercedes, in its entirety, the March 29, 1984 submittal.
l Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely, y '. vr Enclosure ,
cc: Service List 8405300369 840518 PDR ADOCK Q 05000275 PDR fdo j v e-- -- w--- y 4 e _--we--- u-- -
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() I l PGandE Lttter No.: DCL-84-140 ;
ENCLOStlRE RESPONSE TO NOTICE OF VIOLATION ?N NRC INSPECTION REPORT N05. 50-275/83-37 AND 50-323/83-25 1
On February 29, 1984 NRC Region V issued a Severity Level IV Notice of Violation (" Notice") as part of NRC Inspection Report Nos. 50-275/83-37 and i 50-323/83-25 on Diablo Canyon Units 1 and 2.
The " Notice" cited:
e Twenty-eight Pullman employees began inspecting and accepting weldsents prior to completion of required training and certification as welding inspectors.
, DEFICIENCIES IN THE TRAINING AND CERTIFICATION OF PULLMAN WELDING INSPECTORS STATE!ENT OF VIOLATION "As a result of the inspection conducted on McVember 14-18 and November 28 -
December 9, 1983, and in accordance with MRC Enforcement Policy. 10 CFR Part 2, Appendix C, the following violation was identified:
,l Section 17.1.5 of the FSAR (dated October 1978) and the Pacific Gas and Electric. Company Quality Assurance Manual Section V (dated August 15,1978) states, in part, that, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings...and shall be accomplished in accordance with these instructions, procedures, or drawings...." ,
" Engineering Standard Diablo (ESD) No. 237, " Quality Assurance Inspector Training Program," dated February 26, 1974, states in paragraph 2.3 that, "All personnel engaged as Field QA Inspectors involved in the inspection of weldments, interpretation of Engineering Specifications and Welding Procedures, and documentation work, shall be required to complete ar.
indoctrination period as described in Section 4 of this specificatier.."
Paragraph 4.1 states that, "The indoctrination period for the Field Q.A.
Inspectors described in Section 2.3 shall contain as a mininum, but not necessarily limited to, the following courses:
Visual Inspection Welding Procedures Weldin Inspection Welding Processes Basic .A.
Other courses offered as optional are:
Welding Steam Power Plant Fundamentals Basic Power Plan Instruction Introducing Muclear Power Welding)&
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The Visual Inspection and Welding Inspection tests shall be administered and controlled by the N.D.E. Training Officer. All N.D.T. training, qualifications and certifications will be covered by ESD-235."
Paragraph 4.2 states that, " Tests used for the indoctrination courses for Field Q.A. Inspectors shall be:
- 1. For Basic Q.A. Test-ESD's.
- 2. For WeM Procedure Test-Approved Welding Procedures.
- 3. For the D. tid Process Test, Welder Qualification Card and Pipefitter's Manual.
- 4. For Welding Inspection Qualifications, General Welding Information.
- 5. Visual Inspection Qualifications-General Dynamics NDT Introduction."
A Nuclear Services Corporation (NSC) Audit dated October 27, 1977, identified in Criterion IX. Finding No. 3 (of the audit) twenty-eight individuals which were alleged to have begun performing their duties without fulfilling the Pullman Power Products procedural requirements for certification and qualification of Quality Assurance (Welding) Inspectors.
, Contrary to the above requirements of the FSAR and Pullman procedures, the inspector identified on November 15, 1983 that in virtually all cases the individuals hired after September 25, 1973, named in the NSC audit finding (who were assigned to perform welding inspections), began inspecting and accepting weldsents, before completing the required training, taking the i
required examinations, and before being certified as a welding inspector. It j is noted that the Pullman Power Products response to this Nuclear Services l Corporation finding states, in part that, "All current inspectors have been i
qualified by test as outlined in ESD-237. The requirement for qualification and certification of field inspector were added in ESD-237 on September 25, 1973 t'o reflect the requirements of ANSI N45.2.6. just published. Persons hired before this time were not necessarily tested at time of hire.
Subsequent to 1973, the records indicate that all inspection personnel received required training and examination." However, the Pullman response is silent with regards to inspectors performing inspections prior to certification.
This is a Severity Level IV Violation (Supplement II)."
EXPLANATION AND CORRECTIVE STEPS TAKEN The following discusses the corrective measures being taken in response to the issues raised by this Notice. Briefly, we will (1) provide background information concerning Pullman's approach to welder inspector training and qualification; (2) explain the corrective steps taken to address the issue of inspector qualification identified in the NSC audit meeting including the l scope of the reinspection program; and (3) identify any rework of those welds that require modification.
! Prior to January 1973, no requirement or guidance existed within the industry directing the documentation, qualification, or certification of inspectors.
First guidance to industry appeared in ANSI N45.2.6 Standard issued on January 25, 1973. This guidance was subsequently incorporated in NRC Regulatory Guide 1.58. Review of the M. W. Kellogg (" Pullman")
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inter-office correspondence indicates that as of June 14, 1973, they had
, determined that a documented training program was desirable. The development of this program began in September 1973 and the program as described in ESD 237 was approved by PGandE on February 6, 19,74.
In PGandE's investigations, 17 of the 28 individuals cited by the NSC Audit were welding inspectors. The other eleven were non-destructive test inspectors who were fully qualified to perform ND Testing prior to beginning ,
those activities. Pullman Welding Inspectors have been placed into three categories according to their time of hire:
A. Four individuals were hired to perform weld inspections from the start of work through August 1973. All inspectors were qualified to perform visual weld inspections based on a review of documentation of previous work experience and education.
B. the period from l
The files of1,all September inspectors 1973 hired during'980 through December 31, were reviewed. Fifty-three inspectors were hired between September 1, 1973 and October 3, 1975. Of these, seventeen inspectors performed inspections prior to completion of l' the training and testing requirements of ESD-237. After October 3, 1975, all individuals were qualified to ESD-237 requirements before performing inspections.
l I C. One hundred and seven individuals were hired to perform weld inspections from January 1, 1981 to the present. The records of twenty-three of these individuals were reviewed. All years (between 1981 and 1984) were included in this sample. Twenty-one were qualified in accordance with
( ESD-237 requirements prior to becoming inspectors. The remaining two became inspectors one day prior to documentation being placed in their records. This is considered an administrative delay.
These results provide confidence that the requirements of ESD-237 have been fully implemented from October 3, 1975 to date.
Based on documentation of previous work experience and education, all except tw'o individuals who performed inspections prior to documentation of qualification were knowledgeable in welding inspection. We consider these individuals provisionally qualified to perform inspections unless proven ,
otherwise during the reinspection program. Messrs. Guy and Cubbage were not '
considered qualified to perform inspections, based on past experience.
For the 15 inspectors who are provisionally qualified, a sampling of 20% or more of accessible welds inspected prior to compliance with the ESD-237 l procedure is being reinspected. The reinspection is limited to accessible l
welds only. Accessible welds are defined as not being inside concrete, within sleeves, penetrations, or on heat traced lines. If more than one percent of i the welds reinspected for any individual is rejected, the reinspection program )
l will continue until a rejection rate of 15 or less is achieved, or 1005 of the accessible welds inspected by this individus1 have been reinspected.
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,- For Messrs. Guy an(u'Cubbage, all accessible welds inspected prior to qualification are being reinspected.
, These welds were originally inspected to B31.1 and B31.7 requirements. At that time, the codes required a minimum socket weld size of 1.25xt (t= nominal piping wall) but not less than 1/8 of an inch. The welds were measured with a variety of methods, including visual inspection, straight edge rules, handmade weld gauges, or Palmgren Gauges designed for measuring 900 structural steel fillet welds. Inspectors used interpolation of the scale markings while rotating the scale around the socket weld.
- The reinspection program is being performed in accordance with B31.1 (1967) including the Summer 1974 Addendum, B31.7 (1969) and ASME Section III which requires a minimum socket weld size of 1.09xt (t= nominal piping wall). The reinspection uses Fibremetal weld gauges which are more accurate than previous methods.
Attachments A and B summarize the inspection scope and results to date.
During the reinspection program,1059 welds have been reinspected.
Fifty-seven are suspect.
The suspect welds are, in general, on small bore piping. Ninety-five percent are socket welds connecting adjacent piping spools. Two are butt welds connecting 4-inch to 6-inch pipe. The remainder connect stanchions or lugs to the pipe.
Suspect welds found by welding inspectors will be reinspected by supervisory level welding inspectors. If the suspect condition is verified by the supervisors, the weld will be rejected and referred to Engineering.
Engineering will either accept the welds based on analysis or the welds will be repaired.
A high' level of confidence in the quality of work being reinspected is
- established by
- 1. All Code Class A and B, and pressure retaining Code Class C welds were inspected using NDE methods by qualified individuals in addition to the visual inspections.
- 2. In some cases, the welding inspection was witnessed by the Authorized Nuclear Inspector.
- 3. All Design Class 1 piping has been hydro-tested and, in some cases, reinspected for the base line data as a part of the Inservice Inspection Program.
CORRECTIVE STEPS WHICH WILL BE TAKEN Weidments are being re-inspected for acceptability by qualified inspectors in accordance with the above discussion. Should any of these welds be unacceptable, they will be repaired in accordance with the existing approved procedures or the basis for acceptance will be established.
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'DATE WEN FULL C0rLIANCE WILL BE ACHIEVED
, Full compliance with procedure ESD-237 has been in effect since October 3, 1975.
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PGandE plans to complete all corrective action within 30 days for Unit 1, and 60 days for Unit 2 of the date on this submittal. A final report detailing the results of all inspection activities and the disposition of suspect welds will be submitted for Unit 1 and Unit 2 after completion of all corrective action.
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(.- PGan Letter No.: DCL-84-140 Attachment A REINSPECTION PROGRAM FOR PROVISIONALLY QUALIFIED IN5PECTORS(l)
Minimum No. of No. to be Name Inspections (2) ReinspectedReinspected (3)No. Already(4) Suspect (5)
Allmendinger 69 14 31 1 Bloom 2 2 2 0 Bowlby 387 78 117 7 Boyd 192 39 51 1 Finch 289 58 114 4 Jennings 423 85 96 4 Kaz 3 3 1 0 Kincade 84 17 23 2 Page 149 30 42 2
] Pennie 294 59 81 2 0'Brien 2 2 2 0 Sarvwatari 313 63 72 1 Silver 47 10 11 0 Thomas 17 10 10 0 Willard 367 74 135 16 2638 544 788 40 NOTES
- 1. These results have been revised and updated from the March 23, 1984 (DCL-84-115) and March 29, 1984 (DCL-84-124) submittals and are correct '
as of April 10, 1984.
- 2. No. of inspections - Number of weld inspections prior to meeting the requirements of ESD-237.
- 3. No. to be reinspected - 20% or more of accessible welds which are being reinspected.
- 4. No, already reinspected - progress of program to date.
- 5. Suspect - Welds which have been referred to Supervision for review against code tolerances.
0778d/0009K
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, Attachment B REINSPECTION UNQUALIFIED IR5PECTORS PROGRAM FOR(I)
Minimum No. of No. to be No. Already Name Inspections (2) Reinspected (3) Reinspected (4) Suspect (5)
Guy 300 300 260 16 Cubbage 23 12 11 1 323 312 271 17 NOTES
- 1. These results have been revised and updated from the March 23, 1984 (DCL-84-115) and March 29,1984 (DCL-84-124) submittals and are correct as of April 10, 1984.
- 2. No. of Inspections - Number of weld inpsections prior to meeting the requirements of ESD-237.
- 3. No. to be reinspected - All of accessible welds which are being reinspected, i
- 4. No. already reinspected - Progress of program to date.
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- 5. Suspect - Welds which have been referred to Supervision against Code l tolerances.
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