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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
[Table view] |
Text
h Bulletin Reply 79-02 Docket Hos. 50-275/323 PACIFIC GAS AND E LE C T RIC C O M PANY 77 HrALE S T 4 F L T, SAN F L A N C. l S C O . C A l i F O R r41 A 94106 TF LE PHONE (415) ' 81 -4 ? l l
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JAc S 'AL7 2 ". March 12,1982 JOSEPH I MEltY W -
fir. R. H. Engelken, Regional Administrator E 4 Office of Inspection and Enforcement
- Region V Cl RECEIVED ,3 3 U. S. Nuclear Regulatory Conaission 2 w- --:
1450 ffaria Lane, Suite 210
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T E 3 Walnut Creek, CA 94596 - nyffg 6- 4j l Re: Docket No. 50-275, OL-DPR-76 % g g Docket No. 50-323 y g Diablo Canyon Units 1 and 2 Pipe Supports Base Plate Design -- IEB-79-02 $.
Dear f1r. Engelken:
This is an interia response to your letter dated February 5, 1982 (attached). We are preparing procedures to perform tests and review quality control records to provide you with the information requested in your letter.
The attachment to this letter is pr .vi.'ed as a brief status report and contains an outline of PGandE's p.T a 1 iction and the status of the review of IE Bulletin 79-02. We expect ,,aaplete our work for Diablo Canyon Unit 1 and provide you with a ff* ' report, containfrig the information requested, by April 30, 1982. The .ork and final report for Unit 2 will be completed at a later date.
Very truly yours, Attachment b s /
cc (w/ enc.): Service List 8203220312 820312 PDR ADOCK 05000275 h\
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l ATTACHMENT (The numbers below correspond to the items listed in Attachment I to the February 5,1982 NRC letter) 1.1 Completion of Modifications for Unit 1 We have completed the Diablo Canyon Urlt 1 pipe support modiff-cations required to comply with the NRC I&E Bulletin 79-02, excluding resolution of issues raised by the February 5,1982 NRC letter.
1.2 Completion of Modifications and Analysis for Unit 2 The Unit 2 pipe support analysis and modification are 10% com-plete.
- 2. Current Status of Unit 2 Modifications Unit 2 modifications are approximately 10% complete.
- 3. Cyclic Loads No additional response required.
4.1 Preload and Embedment Depth The number of stud-type expansion anchors installed before August 1977 will be detemined from quality control records. We will then measure by sample testing:
o Existing preload (by torque-wrench method), and o Embedment depth (by ultrasonic testing).
4.2(a) "Almost Exclusively" Our records will be reviewed to determine the percentage of shell-type and stud-type expansion anchors used at Diablo Canyon before 1977. This will quantify the "almost exclusively" state-ment in our December 3,1980 letter to you.
4.2(b) Thread Engagement The stripping-strength for shell-type anchors will be determined by test. The load capacity of each type of shell expansion anchors used will be measured to verify that engagement of four threads provides stripping-strength that assures a minimum safety factor of 5 above design load.
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- 5. Use of Expansion Anchors in Concrete Block Walls No additional response required.
- 6. Structural Steel Shapes Instead of Base Plates The relative percentage of pipe supports which have bases made of structural steel shapes instead of plates, will be deter-mined. These were previously reviewed for compliance to IE Bulletin 79-02.
NOTE: In our review of pipe supports with expansion anchors and bases made of structural steel shanes, we have taken into account the flexibility of structural shapes, and we have com-plied with the safety factors required between bolt design load and bolt ultimate capacity.
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8 o NUCLEAR REGULATORY COMMISSION
1440 BAAfuA LANE. Surft 240 e WuAufLIT CIMEK. CALP00BaA 94594
February 5, 1982 Docket Nos. 50-275 [l3bE0 3" "-UI3 50-323 ((i3.0 !!d
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Ju P. O. Box 7442 ya p; a San Francisco, California 94120 .it t m.i p'j..,
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""'""3 Attention: Mr. Philip A. Crane, Jr. ccw uvy txi.a con 0:sim Assistant General Counsel RLK f!LE:
Gentlemen:
Subfact: COMMENTS ON PG&E RESPONSE TO IE BULLETIN 79-02, " PIPE SUPPORT BASE PLATE DESIGN USING CONCRETE EXPANSION ANCHOR BOLTS" Re f: (a) IE Bulletin 79-02, " Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts" of March 8,1979 (b) PG&E letter of December 3,1980, Re: NRC IE Bulletin 79-02, Rev. 2 (c) NRC letter of November 28, 1979 Re: Consnents on PG&E Response to IE Bulletin 79-02 (d) NRC letter of October 9, 1980, Re: NRC Inspection at Diablo Canyon (e) PG&E letter of July 20,1979, Re: Diablo Canyon Units 1 and 2 (f) PG&E letter of September 19, 1979, Re: Diablo Canyon Units 1 and 2 l
The subject bulletin, reference (a), requested PG&E to perfonn certain actions to verify accurate design loads and adequate installation of concrete expansion bolts used in seismic Category I pipe supports and to report the results of those actions to the NRC. Subsequently, Revision 1, Supplement 1, and Revision 2 were issued which provided some details, clarifications, and in the case of Revision 2, new requirements. Refer-ence (b) is the current PG&E response to IE Bulletin 79-02. Reference (b) also responds to references (c) and (d) which were NRC comments to references (e) and (f), PG&E's initial responses to the bulletin.
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FEg 5 1982 Your referenced responses to IE Bulletin 79-02 have been reviewed by the NRC Region Y staff. However, before we can complete our evaluation of the actions you have taken in response in the requests contained within IE Bulletin 79-02, it will be necessary for you to provide us with the additional infonnation identified in Attachment I of this letter.
To enable NRC Region V to complete a timely review of your IE Bulletin 79-02 actions, please submit to me the information identified in Attachment I prior to March 12, 1982.
ng e O gio 1 dministHa tor
Attachment:
As Stated bec: CPUC Applications 49051 and 50028 bbec: Diablo Distribution NOTE: MR. J. B. HOCH - Please prepare reply s
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. _ _ - , , . , . - . , - . - - - - ~ ~ - - - ~ ~ ' * ~ ~' #- -
i NRC RV Review of PG4E Responses to IE Bulletin 79-02 The specific requirements of IE Bulletin 79-02 and the corresponding PG8E responses are sumarized below. Additional information required by NRC Region V to continue its review of PG&E actions taken is identified.
- 1. Bulletin paragraph 1: Verify. pipe support base plate flexibility was accounted for in the calculation of anchor bolt loads. A description of the analytical model used is to be submitted.
PG&E Response: Base plate flexibility has been taken into account in the calculation of bolt loads. Teledyne Engineering per-formed the calculations for 1376 pipe supports for Unit 1.
The analytical model used has been provided. A number of supports in Unit I required modification.
Information Reouired by NRC Reg'( _:
- 1) Notification of completion of modifications for Unit 1.
- 2) Notification of completion of analysis and modifications for Unit 2.
- 2. Bulletin paragraph 2: Verify minimum anchor bolt factors of safety have been achieved.
PG&E Response: The bulletin safety factors have been verified in the calculations of the anchor bolt loads for Unit 1. 241 pipe supports required modifications for Unit I to achieve the factors of safety.
Information Required by NRC Region V: Current status of Unit 2 modifications.
- 3. Bulletin paragraph 3: Describe the design requirements for cyclic loads.
PG&E Response: The load combinations used to calculate bolt loads l are described.
l Information Required by NRC Region V: None
- 4. Bulletin paragraph 4: Verify from existing QC documentation or from a sampling testing program that anchor bolts are preloaded i and are properly installed.
PG&E Response: The preloading of shell type anchor bolts was verified by a field test sample of shell type anchors. For Hilti Kwik Bolts and other stud type anchors PG&E states that Attachment I Page 1 of 3
l e a
the torque values specified in the 1973 Edition of the Phillips Red Head Anchoring System Catalog were applied since August of 1977. For stud type anchor installations prior to August of 1977, acceptance of preload is based on the sampling done on shell type anchors.
Discussion:
' The bulletin requires some specific QC documentation that anchors are torqued to at least design load and that proper embedment is achieved after torquing. The PG&E position, in paragraph 3.F. of Attachment I to reference (b), states that Kwik bolts were installed with an " average filter installation torque" prior to August of 1977, when a torque value was first prescribed at Diablo, and that the " average filter installation torque" for stud type anchors had been detemined by testing the shell anchors of that period. The PG&E position does not address the fact that, while shell anchors do not have a tendency to pull out of their holes, Kwik bolt or stud type anchors do have that tendency. Experience has shown that craftsmen tend to stop torquing once a stud anchor tended to pull out of its hole. Paragraph 7 of Attachment I to reference (b),
states' that starting in 1977 stud type anchors were installed per " Instruction Number 98, Revision 0 dated January 21, 1977, which mandated...embedment depth". As previously pointed out in reference (d), Instruction Number 98 of January 21, 1977 did not mandate embedment depth-or torque. These requirements appeared in the July 27, 1977 revision. In regard to proper installation of Kwik bolt (or stud type) anchors, it does not appear that sufficient verification was provided which assures that embedment depths assumed in analysis were achieved in the field installations.
In reference to shell type anchors (e.g. HD0 or Phillips Red Head Self Drilling) further clarification is required regarding thread engagement adequacy. Re.ference (b), Attachment I,
paragraph 4c references J. E. Shigley "Nechanical Engineering Design" 3rd Edition, Section 6-8, page 252, as the justification that only three threads of engagement are necessary to achieve
! full bolt strength. The discussion by Shigley is general in nature and does not address specific material or application.
The inspector's calculations for sample sizes of Phillips Red Head Anchors show that approximately five threads of engagement are required for full bolt strength, but that four threads of engagement will provide sufficient bolt stripping strength to i provide factors of safety from three to four above the maximum allowable design loads listed in reference (b), Attachment II.
Reference (b) Attachment I, paragraph 7 states that prior to 1977, shell type anchors were "almost exclusively" used.
Attachment I Page 2 of 3 l, -- - - - . -- - - - - - - - - - - - - - - - - -
Infornation Required by NRC Region V:
(1) Fcr stud type anchors - Verification, from existing QC documenta-tion or from a sampling testing program, that stud type anchors installed prior to August, 1977 are preloaded to design load and are properly installed (correct embedment depth, torque, etc.).
(2) For thell type anchors - a numerical quantification of the term "almost exclusively", and an assessment of the stripping strength factors of safety achieved at Diablo Canyon for shell type anchors.
- 5. Bulletin paragraph 5: Determine the extent that expansion anchors were used in concrete block walls.
PG&E Response: No seismic Category I' piping systems are mounted on concrete block walls using expansion anchors.
Information Required by NRC Region V: None
- 6. Bulletin paragraph 6: Determine the extent that pipe supports with expansion anchor bolts used structural steel shapes instead of base plates and verify the steel shapes are included in the bulletin actions.
PG&E Response: None Informa,fon Required by NRC Region V: PG&E needs to provide a response to IE Bulletin 79-02, Rev. 2, paragraph 6.
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Attachment I Page 3 of 3
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