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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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20245F9511989-06-29029 June 1989 Provides Followup to 890613-15 Meetings.Updated BNL Sensitivity Calculation on Plant Initiator Frequency,Losw Encl in Response to Items That Need to Be Addressed ML20247M6851989-05-0101 May 1989 Forwards Comments of Aki,Archuleta & Day on long-term Seismic Program at Facilities,Per 890301-03 Meeting in San Francisco,Ca ML20211D5971983-04-11011 April 1983 Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4 ML20209B7261982-09-10010 September 1982 Submits Addl Info on Model B.Multiple Response Analysis Was Carried Out for Study Purposes Only,As Response Not Presently Acceptable Methodology for Licensing Requirements. Results of Study Not Included ML20212L1961982-03-24024 March 1982 Discusses Results of Util two-dimensional Model Described in Urs/Blume Diablo Canyon Nuclear Plant Unit 1 Containment Structure,Dynamic Seismic Analysis for 7.5m Hosgri Earthquake Dtd May 1979 ML20039G2491981-12-28028 December 1981 Forwards Pnl Review of Util Facility Emergency Plan ML19338D2661980-09-17017 September 1980 Forwards Lighting Maps of Protected Area of Facility in Response to NRC Request.Maps Withheld (Ref 10CFR2.790) ML19331B5421980-06-24024 June 1980 Forwards 800612 First Draft Rept, Dynamic Analysis of El Centro Steam Station Unit 4 for Imperial Valley Earthquake. 1989-06-29
[Table view] |
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", Lawrence Uvermore National Laboratory lg t_
j NUCLEAR SYSTEhis SAFETY PROGRAM May 1,1989
Mr. Robert L. Rothman Structum! & Geosciences Branch Division of Engineering & Systems Technology Office of Nuclear Reactor Regulation Mail Stop 8 D22 .
U. S. Nuclear Regulatory Commission Washington,D.C. 20555 bearBob:
Please find attached the comments of Professors Aki, Archuleta and. Day on the Diablo Canyon Long Term Seismic Program Meeting of March 1-3,1989,in San Fransisco. '
Sincerely, g>
.Savy Engineering Geosciences Attachments cc: L. Reiter Professor Aki Professor Archuleta Professor Day An EqualcworturtyEttplanv e lhesttyof Castome
- R 80B Liamcre. Cattma 94550
- Twx 910-385-8339 UCLLL LWR
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i DEPARTMENT OF GEOLOGICAL SCIENCES [f @
TnEPHONL (213) 743-2717 (e3-[
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9' March 1989-1
!: . j Dr. Jean Savy l MS L-196-
.LLNL P.O.~ Box 808 L Livermore, CA 94550
Dear:
Jean:
This is my letter report on .the 1-3 March 1989 meeting on j ground motions of the Diablo Canyon Long Term Seismic Program. !
My general impression of the meeting is that this was, by far, i the best meeting of LTSP because of the high quality of presen- l tations and well-focused discussions that followed. I enjoyed !
both presentations and discussions very much. In the following, I shall state my positions on several key issues discussed in the meeting. !
(1) Let me start with the selection' rule fo,r earthquakes used in empirical investigations. The choice of the magnitude-- i distance range is rather arbitrary, and needs some perturbation to see how sensitive the final result depends on the choice. . I '
am particularly interested in extending the magnitude range down to 6.0, so that the Parkfield and Morgan Hill earthquake
'are included.
(2) I am very much intrigued by the magnitude dependence- ;
of the empirical standard error of PGA and Sa. At first, I thought that the artifact of data set, namely the dominance of intraevent data for larger M and dominance of interevent data f or smaller M was causing the apparent magnitude dependence. .
In that case, the small standard error adopted by P.G. and E. i may underestimate t.he true error-because of the small number of l- events used f or analysis. On the other hand, the analysis of n
Taiwan array data by N. Abrahmson, which is free from the i interevent-intraevent artifact, also shows a systematic trend of the decreasing error with the increasing M. Furthermore, as Steve Day pointed out in the meeting, such a trend may be expected from the physics of phenomena because seismic motion due to a large earthquake will have contributions f rom various ;
parts of the f ault plane, and they tend to average and smooth the ef f ect with resultant less variable motion among earth-l-
I quakes than smaller earthquakes with distinct characters. In view of these arguments, I consider that the standard error used by P.G. and E. is acceptable. i 1
UNIVERs1TY OF SOUTHERN CALIFORNIA, UNIVERSTIY PARK. LOS ANGELES, CAUFORNIA 90089-0740 l
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(3) With regard to the numerical modeling, I think that the e m p-i r i c a l source function is mis-named. This is not representing the source effect, but is simply empirical Green's function corrected for the propagation effect in a very crude manner I believe that'" reduced empirical Green's f unction" may be.a better name. Since the current name mpy cause'a ~
. serious mis-use of the method. I consider the, renaming.
important.
(4)'As I understand now, the potential earthquake from the Hosgri fault is modeled by 4x22 subevents distributed oger the fault pla'ne, each subevent occupying the area-3x4 km . The seis g 5x10gie moment dyne cm, of andthethe' subevent (Imperial seismogram was Valley modified aftershock) to have isa cornerThis.
f requency corresponding to the Brung stress drop of 50 stress drop matches the.3x4 km fault area to be l bar.
occupied by the subevent. This impl s that an average slip of about 10 cm: (5x10y/(3x10yphe, x3x4x10 subevent 0)).. has In order to scale the rise time, 17 subevents are delay-summed to give rise to the total rise time of 3.5 sec. This means that the total slip of 170 cm occurs within 3.5 sec, corresponding to the slip velocity of 50 cm/s and, in turn, to the local st ress drop of- about 50 bar. In this case, the moment scale factor c is very nearly 1, and there is no need for further modifying the subevent. ,
Thus, the final picture is a fault plane filled with 4x22 subevents each occupying 3x4 km2 area, with the slip-velocity of .50 cm's. and local stress drop of 50 bar. Since the stress drop varies from place to place considerably in their asperity
( model, the. strongest asperity may have local stress drop of a few c '-ed bars.
The above model is quite similar to models used for older
_(before 1979) earthquakes in California by others such as Hanks and McGuire, and Papageorgiou and Aki. Their validation result using-data from three recent earthquakes is encouraging and persuasive to extended it to the Hosgri fault.
(5) The deficiency of predicted low frequency response spectra due to the lack of near-field and surf ace wave contri-butions must be clearly stated with the precise statement about the frequency range in which the deficiency is significant.
The display of final result should also distinguish this uncer-tain part from the reliable part using, say, a dashed line.
(6) In the step-by-step explanation of errors (dispersion) in the numerical simulation, non-zero estimates of mean diffe-rence'between observed and predicted were mentioned f or the 2
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.I'am~ enclosing claim for consulting services.
Sincerely-yours, Keiiti Aki
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STEVEN M. DAY
- DEPARTMENTOF GEOLOGICAL SCIENCES SAN DIEGO STA1E UN!VERSITY SAN DiEGO. CA 92182 (619)594-2663 or 594-5586 April 19,1989 Jean Savy
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Lawrence Livermore National Laboratory P. O. Box 808 Mail Stop L-196 Livermore, Califomia 94550
DearJean:
The following is my report on the San Francisco meeting of March I through March 3 between the NRC staff and consultants and P.G. and E. The purpose of the meeting was to review the P.G. and E. responses to NRC questions raised during the review of the ground motion component of the Diablo Canyon long Term Seismic Pmgram. .
This was a very productive meeting,in which a large number ofimportant questions from the NRC staff and consultants were addressed in considerable depth. The staff and consultants of P.O. and E. did an outstanding job of communicating the results of this lengthy, complex, and innovative program. I will comment separately on the empirical and numerical components of the ground motion studies. -
Empirical Ground Motion. The empirical ground motion analysis has two components, regression analysis and statistics of the near-field data set, respectively. With respect to the ,
former,I see no problems. There was broad agreement between the Geomatrix regression results l and those of Ken Campbell. In particular, the following conclusions were common to both studies,in spite of somewhat different methodologies employed: i) Ground motion variance is about 0.4 natural log units, and is approximately frequency independent. ii) Thrust mechanism gives mean ground motion about a factor of 1.2 greater than strike-slip. iii) Regression of Sa/PGA is an appropriate procedure, given the non-uniformity of the data set in the magnitude-distance plane. iv) The vertical acceleration response spectrum is peaked at a considerably higher frequency that was the 1977 Newmark spectrum, and substantially exceeds the Newmark spectrum above about 8 Hz. In addition, the thrust / strike-slip ratio was further validated using the numerical model.
I also believe that the discrepancies between Professor Veletsos's analysis and the P.G.
and E. analysis of the near-field data set have been resolved, since the data set analyzed by Professor Veletsos was constructed for use in fragility analysis, and was deliberately weighted towards records with high values of Sa averaged over the 3-8 Hz band.
I still have a few reservations regarding the analysis of the data set of near-field recordings.
I recognize that, because the response spectrum derived from regression analysis envelopes the spectrum derived from analysis of the near-field data set, these reservations of mine may not
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significantly affect the conclusions of the LTSP, but I want to put them on the record anyway. The first concem is that the selection criteria for the data set were applied sufficiently rigidly to exclude the Morgan Hill and Parkfield earthquakes, but sufficiently permissively to include 5 records from the Imperial Valley. I don't find the logic for excluding Morgan Hill and Parkfield (rock sites, M>6), then adding Imperial Valley (soil sites, M>6.25) to be persuasive ( although I am somewhat reassured by Professor Aki's observation that the empirical attenuation exponent x0 is similar between sites on Franciscan geology and sites in the Imperial Valley). .
Secondly,I am not satisfied that topographic amplification of the Pacoima Dam recording of the San Fernando canhquake is established with sufficient certainty to justify the reduction factor which was applied. Anooshehpoor's thesis (U.C.S.D.,1988) presents three-dimensional physical modeling results which call this conclusion into question. In panicular, he finds that, depending upon angle of incidence, either amplification or deamplification is possible at the Pacoima Dam site.
All of the empirical studies probably substantially underestimate the true uncertainty in ground motion, since i) they reflect the dispersion of the residuals, but not the uncenainty in the regression coefficients, the latter being an increasingly imponant factor at shon distances (i.e., far '
from the centroid of the data), and ii) they operate on averages of the two horizontal components.
As I understand it, however, these two procedures are conventionally accepted by the NRC.
Numerical Ground Motion. Overall, I suppon the numerical modeling procedure being used, and I believe it is generally appropriate for frequencies above about 3 Hz. The method presented for quantifying the uncenainty ir, the numerical ground motion estimates was innovative, and represents a real step forward for the numerical approach. The conceptual separation of the dispersion into " random and modeling" error plus " parametric uncertainty" is intuitively appealing and informative. The fact that the composited dispersion estimated in this fashion agreed well with the observed dispersion, as estimated from the empirical studies, was a notable result.
The finite difference calculations of site effects at the Diablo site showed no significant topographic effect. These results would be more convincing if they were repeated for SV incident energy,instead of SH. This would be consistent with the SV calculation performed for the analysis of possible topographic effects at Nahanni Site 2. Simple physical arguments suggest that SV amplification should be the worst case; in addition, previous published numerical studies of topographic amplification show the SV case to generally produce more amplification than the SH case (Geli et al., BSSA vol. 78).
Sincerely, Steven M. Day
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- MN MECO e MN FMNCnCO f SANh MRMRA . SAM CRUZ DEPART MENT OF GLOLOGICAL SCIENCES SANTA BARBARA. CALIFORNIA 93106 April 11,1989 Dr. Jean Savy Mail Stop L-196 Lawrence Livermore Laboratory
' P. O. Box 808 Livermore,CA 94550
- RE: Diablo Canyon Nuclear Power Plant Meeting of March 1,2,3,1989
Dear Jean,
, Without doubt this meeting was probably the most informative of any that I have attended regarding the Diablo Canyon Nuclear Power Plant (DCNPP). While it did not lay to rest some questions that I have, it did make much clearer what PG&E was doing to examine the seismic ground motion.
- Although Issue 11 of Harry Rood's letter of March 17,1989, addresses the issue of the response spectrum from the numerical simulations being deficient at the lower frequencies, I want to change the question a little. Paul Sommerville said that their target i frequency range was 3.0-8.5 Hz. What would happen to the peak acceleration if the low frequency (less than 3.0 Hz) were matched as well as the 3.0-8.5 range? I would guess that if the low frequencies wem included, the peak acceleration would be higher. The high frequency components would be riding on the low frequency components. I don't know how much of a difference it would make, but to assume that the peak acceleration is unaffected by the loss of the low frequency components seems wTong.
The second point about the low frequency components is that these components are the ones that will show directivity. The frequency-dependent radiation pattem used by PG&E will not alter these frequencies very much. I would expect that these components will show a directivity effect,i.e., an increase in amplitude in the direction of propagation, especially the east-west ground motion. Thus the lack oflow frequency energy m the numerical simulations probably has a significant effect on the results.
I would like to see a tabulation for the numerical simulations boken down by cases, e.g., unilateral strike-slip with Coalinga empirical source. The infonnation to be tabulated for each station am the peak ground acceleration, the aver.sge acceleration response spectra for each component (vertical, East-West, North-South). Each table would have a formatlike:
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Case 1: Unilateral Strike-Slip, IV Empirical Source Station # PGA Avg. Response 3-8.5 Hz Avg. Response 5-14 Hz V E-W N-S V E-W N-S V E-W .N-S 2'
Total: V E-W N-S V E-W N-S V E-W N-S The reason for this request is that in reviewing PG&E's response to Question 18, I noticed that the Coalinga source almost always generates larger response spectral values than the Imperial Valley source. Also the East-West component is generally larger than the North-South. For the strike-slip scenario directivity would affect the East-West component. The final response spectrum is the average of all these components for all the simulations. I don't know if the NRC requires an average of components, but it seems that the North-South component is almost always less than or just equal to the East-West component. If the structures are more susceptible to East-West motion, then the average spectmm may be misleading. The averaging is producing a mediari spectmm, but I wonder what the individual averages look like for the different cases that were mn.
The fact that Coalinga generates larger spectral values leads me to wonder how representative the two empirical sources are. Is Coalinga a maximum? Is Imperial Valley a minimum?
The method of computing random realizations by using vadous stations distributed along strike seems clever to me. I don't know whether these simulations represent the true range of possibilities for a M 7.2 earthquake. The simulations represent a periodic spatial variation of slip along strike (see attached plot). There are other physical parameters that were not varied. There is only one rupture velocity used; there is only one rise time used; there is only one stress drop used. While the rise time and stress dmp are related to acceleration in an approximately linear fashion, the rupture velocity is nonlinearly related. The rupture velocity used by PG&E is almost constant, the three sigma factor practically guarantees it. Thus all the radiation comes from the slip distribution. A rupture velocity that accelerates or decelerates could produce accelerations equal to or greater than the slip (Bernard and Madariaga,1984; Spudich and Frazer, 1984).
I am still confused about how PG&E determined the number of subevents. Paul Sommerville presented a viewgraph showing that N t = T/ t = 3.3 / 0.2 = 17. Clearly the rise time of the 4 x 3 element is 3.5 seconds and the rise time of the individual subevents within an element is 0.2 seconds. However, my notes indicate that PG&E used t = 0.6 and not 0.2 seconds. The 0.2 seconds is appropriate for a 400 bar stress drop for the 23:19 IV aftershock. To get that stress drop to 50 bars as stated in response to Question
O 12 PG&E applied a Brune filter. I presume that they mean (I would like this made more 7, clear by having Pg&E show an example.) that b cause stress dr@ is proponional to comer frequency cubed (Brune,1970), to reduce 400 bars to 50 bars the corncr frequency
- of the IV aftershock was reduced by a factor of 2. If the original rise time was 0.2 seconds corresponding to 400 bars, then the new comer frequency is 0.4 seconds corresponding to 50 bars. In which case the number of subevents is 9 and not 17. The number of subevents becomes important because the slip of each subevent is the total slip divided by Nr. 'Ihus an element with 10 m of slip has 0.62 m with each subevent whereas ~
with 9 subevents the slip is 1.1 m. Each subevent is radiating a larger amplitude pulse which could lead to larger amplitude ground motion. I would like a very clear explanation of which numbers were used and why for both the IV aftershock and the Coalinga aftershock. I would like to see the displacement amplitude spectra for Coalinga from which PG&E deduced the corner frequency (rise time) and stress drop. The IV aftershock is based on the paper of Liu and Helmberger, but I don't recall seeing an analysis of the May 9 Coalinga aftershock. Does it have the same stress drop as the IV aftershock? the same corner frequency? the same moment? In other words, how does PG&E demonstrate that these two empirical source functions are similar?
Issue 3 of Rood's letter focusses on another issue that I have strong feelings about. Slip in the upper three kilometers is likely to produce significant surface waves that '
are not modeled by the incomplete Green's functions being used for the numerical simulations. Although PG&E provided many examples of slip distributions inferred from inversions of teleseismic data, these examples miss the point. How many crustal earthquakes with M 7.2 have failed to produce surface slip? How large might that surface slip'be relative to that at depth? PG&E indicates zero. If so, how does the upper three kilometers of earth manage to decouple itself from the rest of the earth? The examples shown by PG&E were for magnitude 6 type earthquakes except for Borah Peak which using their example indicates no stu-face slip, completely contrary to the field observations.
Issue 2 in Rood's letter is c;uite broad in its scope. Specifically I would like to see what happens to the attenuation re: ations when the distance criterion is relaxed by 5 and 10 kilometers. Similarly what happens when the magnitude range is allowed to encompass M 6.2, and M 6.1 canhquakes?
A criticism that is directed more toward the NRC is that we have not received any information about the hazard with respect to the style of faulting on th' 'losgri. PG&E is assumir.g 65% strike slip,30% oblique and 5% thrust. From a statistical point of view it may be satisfactory to weight the calculations this way. However, I doubt that nature will follow such a rule. The numerical simulations should not be averaged over all possible mechanisms. Each mechanism should produce its own average ground motion l
parameters. The fact that PG&E has homogenized the radiation pattern for the high frequencies,in essence, averages over fanit mechanisms. The only parameter that is different for the style of faulting is the 5 of Q thlt. I am going to have to think more about what effect the radiation pattem sm%r,iro used by PG&E has on the ground motion. Nonetheless, we on the ground mc *n yn:1 have only one viewpoint as to the probable style of mpture.
1 i Sincerel ,
Ralph J. Archuleta
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