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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212B1681999-09-13013 September 1999 Forwards Insp Repts 50-275/99-12 & 50-323/99-12 on 990711- 08-21.Four Violations Being Treated as Noncited Violations ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H6181999-07-27027 July 1999 Forwards Insp Repts 50-275/99-07 & 50-323/99-07 on 990503- 0714.Apparent Violations Being Considered for Escalated Enforcement Action ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot IR 05000275/19980121999-01-13013 January 1999 Informs That Insp Repts 50-275/98-12 & 50-323/98-12 Have Been Canceled DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld ML20195G5161998-11-16016 November 1998 Forwards Insp Repts 50-275/98-16 & 50-323/98-16 on 980913- 1024.No Violations Noted ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236T2931998-07-24024 July 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities for 5 Yrs.Order Being Issued Due to Falsification of Info on Application to Obtain Unescorted Access to PG&E Plant ML20236T3431998-07-22022 July 1998 Forwards Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.Apparent Violations Identified & Being Considered for Escalated Enforcement Action ML20236J2251998-07-0101 July 1998 Ltr Contract,Task Order 232 Entitled, Review of Callaway, Comanche,Diablo Canyon & Wolf Creek Applications for Conversion to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 IR 05000275/19980051998-04-17017 April 1998 Forwards Insp Repts 50-275/98-05 & 50-323/98-05 on 980202-06 & 23-27 & 0302-18.No Violations Noted.Insp Focused on Resolution of Previous NRC Insp Findings & Included Review of Issues Identified During Architect/Engineering Insp Rept ML20203G0371998-02-25025 February 1998 Forwards Revised Copy of NRC Form 398, Personal Qualification Statement - Licensee, (10/97) Encl 1,which Has Been Revised to Reflect Current Operator Licensing Policy DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld ML20199H6691998-02-0202 February 1998 Ack Receipt of ,Transmitting Rev 18,change 11, to Plant Physical Security Plan,Submitted Under Provisions of 10CFR50.54(p).Role of Video Capture Audible Alarm Sys Needs to Be Addressed in Security Plan,Per 980123 Telcon DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld IR 05000275/19970181997-10-31031 October 1997 Forwards Insp Repts 50-275/97-18 & 50-323/97-18 on 971006- 10.Insp Verified That Liquid & Gaseous Radioactive Waste Effluent Mgt Program Was Properly Implemented.No Violations Noted DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML20134H6271997-02-10010 February 1997 Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5) ML20134K3421997-02-0606 February 1997 Conveys Results & Conclusions of Operational Safeguards Response Evaluation Conducted by NRR at Plant,Units 1 & 2, on 960909-12.W/o Encl ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) ML20129J4001996-10-18018 October 1996 Forwards Order Approving Corporate Restructuring by Establishment of Holding Company & Safety Evaluation NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl ML20129G6121996-09-24024 September 1996 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App C,E,F & G.Documents Available in Pdr.App E,F & G Documents Partially Withheld Ref FOIA Exemptions 4 & 6.App D Record Listed as Copyright DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld 1999-09-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld ML20100L4631996-02-23023 February 1996 Forwards Response to NRC Enforcement Action 95-279 Re Violations Noted in Insp Repts 50-275/95-17 & 50-323/95-17 on 951021-1208.Corrective Actions:Directive Was Issued to Plan 2R7 W/Six Day Work Schedule DCL-96-036, Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr1996-02-20020 February 1996 Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr ML20097E9341996-01-25025 January 1996 Forwards Public Version of EPIP Update for Diablo Canyon Power Plant,Units 1 & 2 DCL-95-272, Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training1995-12-11011 December 1995 Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training DCL-95-264, Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5))1995-12-0606 December 1995 Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5)) ML20094M6001995-11-21021 November 1995 Forwards Final Rept of Investigation & Analysis of Event 29257 Re Substandard Fastner Processed & Sold by Cardinal Industrial Products,Lp,So That Customers Can Evaluate Situation in Light of 10CFR21.21(a)(1)(ii) & (b)(1) DCL-95-204, Forwards Proposed Changes to Physical Security Plan.Encl Withheld1995-09-19019 September 1995 Forwards Proposed Changes to Physical Security Plan.Encl Withheld DCL-95-199, Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan1995-09-14014 September 1995 Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan ML20087A0471995-07-28028 July 1995 Forwards Security Safeguards Info in Form of Change to Proposed Draft Plant Security Program.Encl Withheld DCL-95-153, Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo1995-07-27027 July 1995 Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo DCL-95-134, Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d)1995-07-0505 July 1995 Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d) ML20086H5461995-06-29029 June 1995 Forwards Final Exercise Rept for 931020,full Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response plans,site-specific to Plant.No Deficiencies Noted DCL-95-046, Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld1995-02-28028 February 1995 Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld DCL-95-039, Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo1995-02-23023 February 1995 Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo ML18101A5671995-02-17017 February 1995 Informs of Improper Presentation of Jet Expansion Model in Bechtel Technical rept,BN-TOP-2,Rev 2 Design for Pipe Break Effects Issued May 1974.NRC May Need to Consider Evaluating Consequences of Potential Misapplication of Expansion Model ML18101A5681995-02-17017 February 1995 Requests NRC to Clarify Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 LCO Under Circumstances as Ref in in 95-10.Subj in Re Postulated Slb W/Potential to Render One Train of Ssps Inoperable ML18101A5741995-02-17017 February 1995 Requests Clarification of Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 Limiting Conditions for Operation Under Circumstances Described in Info Notice 95-10 DCL-95-033, Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures1995-02-13013 February 1995 Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures DCL-95-013, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo1995-01-24024 January 1995 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo DCL-94-258, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B1994-11-21021 November 1994 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B 1999-06-25
[Table view] Category:UTILITY TO NRC
MONTHYEARDCL-90-202, Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.91990-08-0707 August 1990 Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.9 ML20043A4131990-05-17017 May 1990 Forwards Response to Violations Noted in Insp Repts 50-275/90-02 & 50-323/90-02 Re Unauthorized Individuals Gaining Access to Vital Areas & Failure to Protect Safeguards Matl.Response Withheld ML20042G6491990-05-10010 May 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML16341F6901990-04-26026 April 1990 Forwards Public Version of Rev 9 to Corporate Emergency Response Plan 4.3, Radiological Analyses & Protection. ML17083C2491990-04-0202 April 1990 Forwards Response to Questions on Geology/Seismology/ Geophysics/Tectonics in long-term Seismic Program Final Rept.Proprietary Data Withheld (Ref 10CFR2.790).W/one Oversize Drawing ML20012E2261990-03-26026 March 1990 Forwards Rev 17 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21) ML20042H0421990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F6431990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Emergency Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F5941990-02-14014 February 1990 Forwards Public Version of Rev 11 to EPIP EP G-4, Personnel Accountability & Assembly. W/900305 Release Memo ML16341F5581990-02-0606 February 1990 Forwards Proprietary WCAP-12495 & Nonproprietary WCAP-12496, Review of Flow Peaking & Tube Fatigue in Diablo Canyon Units 1 & 2 Steam Generators Per El Murphy Aug 1989 Request ML16341F5401990-01-30030 January 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EP M-1 & EP M-6 & Rev 13 to EP G-2S1.W/900215 Release Memo ML16341F5421990-01-29029 January 1990 Forwards Public Version of Rev 7 to Corporate Erpip Update ML20005G0521990-01-0909 January 1990 Forwards Rev 3 to Safeguards Contingency Plan,Per Generic Ltr 89-07.Rev Withheld (Ref 10CFR73.21) ML16341F4351989-11-13013 November 1989 Forwards Public Version of Epips,Consisting of Pages 15,29 & Test Data Sheets to Rev 10 to EP M-4, Earthquake, & Pages 32-1 & 32-3 to Rev 16 to EP M-6, Nonradiological Fire. W/891205 Release Memo ML20246E6061989-08-16016 August 1989 Forwards Endorsements 10 & 11 to Nelia Certificate N-74 & Maelu Certificate M-74 & Endorsements 7 & 8 to Nelia Certificate N-76 & Maelu Certificate M-76,respectively DCL-89-201, Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form1989-07-28028 July 1989 Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form DCL-89-183, Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1989-07-0606 July 1989 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) DCL-89-149, Requests Renewal of Approval of QA Programs for Radioactive Matl Packages1989-05-30030 May 1989 Requests Renewal of Approval of QA Programs for Radioactive Matl Packages ML20244B4881989-04-0707 April 1989 Forwards Endorsement 35 to Maelu Policy MF-103 & Endorsements 65 & 116 to Nelia Policies NF-228 & NF-113, Respectively DCL-89-051, Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo1989-03-0202 March 1989 Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo DCL-89-042, Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21)1989-02-23023 February 1989 Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21) ML20235J2191989-02-17017 February 1989 Forwards Endorsements,Including Endorsement 3 to Nelia Certificate NW-132,Endorsement 3 to Maelu Certificate MW-73, Endorsement 4 to Nelia Certificate NW-51 & Endorsement 4 to Maelu Certificate MW-135 ML16341E8821988-11-30030 November 1988 Forwards Proprietary WCAP-12064, Diablo Canyon 1 & 2 Evaluation for Tube Vibration Induced Fatigue. All Five Tubes Requiring Corrective Action Removed from Svc During Unit 2 Refueling Outage.Rept Withheld (Ref 10CFR2.790) DCL-88-277, Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope1988-11-18018 November 1988 Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope DCL-88-216, Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support1988-09-0202 September 1988 Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support ML16342B4691988-08-0101 August 1988 Forwards Proprietary WCAP-11312, Westinghouse Owners Group Tech Spec Subcommittee Reactor Trip Breaker Maint/ Surveillance Optimization Program. Rept Withheld (Ref 10CFR2.790) DCL-88-128, Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21)1988-05-12012 May 1988 Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21) DCL-88-095, Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21)1988-04-19019 April 1988 Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21) DCL-88-051, Forwards Rev 16 to Physical Security Plan.Rev Withheld1988-03-0404 March 1988 Forwards Rev 16 to Physical Security Plan.Rev Withheld ML20151G1181988-02-22022 February 1988 FOIA Request for Documents Re ACRS Subcommittee Meetings on 750218-19 Re Plant ML20147E3651988-02-10010 February 1988 FOIA Request for Documents Re NRC 750318 Summary of ACRS Subcommittee Meeting on 750218-19 DCL-87-269, Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21)1987-11-0909 November 1987 Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21) ML20236N5361987-11-0909 November 1987 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments 860323-870322. Rept Same as Reporting Interval of Annual FSAR Update Rev ML20236H9691987-10-26026 October 1987 Forwards Endorsement 25 to Maelu Policy MF-103 & Endorsement 55 to Nelia Policy NF-228 DCL-87-249, Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util1987-10-13013 October 1987 Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util DCL-87-216, Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation1987-09-0808 September 1987 Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation DCL-87-202, Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo1987-08-13013 August 1987 Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo DCL-87-159, Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21)1987-06-30030 June 1987 Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21) DCL-87-146, Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21)1987-06-25025 June 1987 Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21) DCL-87-129, Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-11987-06-0808 June 1987 Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-1 ST-HL-AE-2035, Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl1987-04-30030 April 1987 Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl ML20207R4571987-03-13013 March 1987 Forwards Endorsements 52 & 110 to Nelia Policies NF-228 & NF-113,respectively DCL-87-045, Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised1987-03-11011 March 1987 Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised DCL-87-042, Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-0031987-03-0909 March 1987 Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-003 DCL-87-041, Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21)1987-03-0505 March 1987 Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21) 05000275/LER-1985-014, Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip1987-03-0303 March 1987 Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip DCL-87-024, Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-271987-02-12012 February 1987 Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-27 ML20211F5121987-02-11011 February 1987 Informs That Lt Gesinsky Has Become Seriously Ill & Will Not Be Able to Testify,As Witness,On Behalf of Util.Ee Demario Will Replace Lt Gesinsky as Witness.Prof Qualifications Encl DCL-87-014, Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage1987-01-28028 January 1987 Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage DCL-87-006, Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler1987-01-12012 January 1987 Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler 1990-08-07
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- Dc5 l PACIFIC G.A.S A N D EL E C T R,I C C O M PANY j k 77 BEALE STREET = SAN F R A N CISC O, C A LI FO R N I A 94106 G EORGE A. M AN EATIS EntCuTivE WCE MES0fte?
June 15,1984 PGandE Letter No. : DCL-84-228 Mr. R. C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Docket No. 50-275, OL-DPR-76 Diablo Canyon Unit 1 Response to NRC Enforcement Action EA 84-42
Dear Mr. DeYoung:
On May 17,1984, the NRC Region V issued Enforcement Action EA 84-42, comprising a Severity Level III Notice of Violation and Proposed Imposition of Civil Penalty (Notice), for an event that occurred on April 6,1984 Pursuant to 10 CFR Part 2 and in accordance with the Notice, enclosed is PGandE's response to the Notice with a check for $50,000 payable to the Treasurer of the United States. As stated in the Notice, PGandE identified the violation and promptly reported it to the NRC. Further, PGandE also took prompt corrective action to prevent recurrence.
PGandE fully recognizes its responsibility to assure that procedures are adequate and consistent with regulatory requirements, and that operators are fully cognizant and aware of those regulatory requirements. As described in the enclosed response, PGandE believes appropriate and timely actions arc being taken to fulfill these responsibilities.
e406200056 840615 PDR ADOCK 05000275 0 PDR ,
f i
b Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Subscribed to in San Francisco, California this 15th day of June,1984.
Respectfully submitted, Pacific Gas and Electric Company Robert Ohlbach By /.
Philip A. Crane, Jr. / G. A. Maneatis Richard F. Locke Executive Vice President t Douglas A. Oglesby Facilities and Electric Attorneys for Pacific Resources Development Gas and Electric Coirpany Subscribed and sworn to before me this 15th day of June,1984 By ev Q)(( n0N O # F^ *M"t Ndecy' J. L'emdster, NotTry7ublic in SEAL
~ Iougfas A. Oglet5y g
and for the City and County of San Francisco, State of California My commission expires April 14, 1986.
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NANCY J. LEMASTER cc: G. W. Knighton ra/ twrARy punuc CwmRmA [j i]' W.M J. B. Martin %y;- CITY AND COUNTY OF Service List b MN UMNGSCO p My Commission Dp.res April 14,1986 Axxxxxxxxxxxxxxxxxxx:o:xxxxxxx t'
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PGandE Letter No. : DCL-84-228 ENCLOSURE RESPONSE TO NOTICE OF VIOLATION AND PROPOSED :
IMPOSITION OF CIVIL PENALTY NRC ENFORCEMENT ACTION EA 84-42 On May 17,1984, NRC Region V issued Enforcement Action EA 84-42 comprising a Severity Level III Notice of Violation (Notice) and Proposed Imposition of Civil Penalty. The Notice cited:
e Unit 1 Technical Specifications were violated when the Boron Injection Tank (BIT) was valved out of service and electrical power was removed from the valve operators to permit draining and refilling the tanks >:ith 12 percent boric acid solution. This action would have prevented 1.he charging pumps from injecting coolant through the BIT and into the Reactor Coolant System upon actuation of a safety injection signal when in Modes 1, 2 or 3.
STATEMENT OF VIOLATION
" Technical Specification 3.5.2 reads, in part:
'Two Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:...
- a. One OPERABLE centrifugal charging pump,...
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- b. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and manually transferring suction to the containment sump during the recin:ulation phase of operation.
APPLICABILITY: MODES 1, 2 and 3.
- a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the i next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.'
Technical Specification 3.0.3 reads in part:
'When a Limiting Condition for Operation is not met, except as provided in the as:;ociated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the Specification does not apply by placing it, as applicable in:
- 1. At least HOT STANDDY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3 At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.'
1228d/0016K Contrary to the above requirements, on April 6,1984 at about 7:10 P.M., the inlet and outlet valves to the Boron Injection Tank (BIT) were closed and disabled by securing the electrical power' to the valve operators. This action blocked and rendered inoperable the flow path between the centrifugal charging pumps and the reactor coolant system for both ECCS subsystems. The valves were returned to service at about 10:10 A.M. on April 7,1984. The reactor was in Mode 3 at all times during this period.
This is a Severity Level III violation (Supplement' I)
(Civil Penalty - $30,000)."
ADMISSION OR DENIAL OF THE VIOLATION PGandE admits to the Violation as described above.
REASONS FOR THE VIOLATION In the Fall of 1983, Operating Procedure OP B-lC, "12% Boric Acid System" was revised by the operations group, reviewed by the Plant Staff Review Committee (PSRC) and approved by the Plant Manager. At that time, the procedure contained instructions to isolate the BIT in order to recharge it with 12%
boric acid solution. The need to maintain an operable ECCS subsystem in Modes 1, 2 and 3, as required by Technical Specification 3.5.2, was not identified.
The procedure revision was prompted by an event that occurred at and was reported by another operating plant and was subsequently disseminated by the Institute of Nuclear Power Operations (INP0) NETWORK system. The plant had injected the contents of the Doron Injection Tank (BIT) into the Reactor Coolant System and, in the process of refilling the BIT, had left the isolation valve circuit bmakers closed. If a second safety injection signal had been received, the valves would have opened and the charging pumps could have tripped out due to pumping into an empty BIT. The NETWORK entry concluded by recommending that other operating plants consider either opening their isolation valve breakers when recharging the BIT or by restoring the boric acid concentration by recirculation of the BIT with the Standby Boric Acid Tank.
Prior to beginning tests of the steam generator safety valves, a temporary operating procedure was written and approved covering the anticipated safety injection and recovery operations. The procedure specified use of Operating Procedure OP B-lC to accomplish recharging of the BIT. As expected, a safety injection occurred on April 6,1984, during the steam generator safety valve tests. The safety injection resulted in disch1rge of the BIT, which was subsequently recharged in accordance with Operating Procedure OP B-lC while in Mode 3. As noted, the recharging operation was performed with the BIT isolated, thus rendering both ECCS flowpaths inoperable for approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and in violation of Technical Specifications 3.5.2 and 3.0.3.
CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND RESULTS ACHIEVED Upon discovery, during routine control panel walkdown, that both ECCS subsystems were inoperable, the circuit breakers to the BIT isolation valves were closed, thus mestablishing the required flow path. The event was reported to the NRC Operations Center within one hour by telephone in accordance with 10 CFR 50.72 and a Licensee Event Report was submitted within 30 days.
1228d/0016K
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A new operating procedure " Restoring Boron Injection Tank After Safety Injection", was issued to allow rechargjng of the BIT without exceeding Unit 1 .
Technical Specifications. Additionally, all operating procedures involving !
! equipment subject to technical specification limitations have been reviewed in i order to identify and correct similar situations.
! A Senior Operations Engineer, Shift Foreman, and Senior Operator Training ,
i Instructor visited the Trojan and San Onofre Power Stations to review the L methods used by these plants to control the configuration of Engineered l
- j. Safety Features (ESF) equipment. An evaluation of these methods has resulted ;
in the, initiation of modifications to several Diablo Canyon Power Plant t operating procedures.- :
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- To further help assure tha technical adequacy of plant procedures, Administrative Procedure E-4, Procedures, was revised on June 11,1984 to add e the requirement to conduct an independent technical review for operating, i emergency, testing, maintenance, chemical, and radiochemical procedures with
- substantial technical content. This review will be perfomed by a i i knowledgeable individual selected by the appropriate department head. The t l reviewer shall not be the author, but may be the author's line supervisor. ;
The independent reviewer will be responsible (along with the author) for }
- assuring that
The procedure will accomplish the desired results, t i - Techr.ical Specifications, cautionary notes, and other such references are
- clearly specified so that the user is not misled. !
1 -
Setpoints, valve numbers, limits, and other such infomation are correct.
The procedure is clear and unambiguous.
- Technical Specifications and other license conditions are complied with. !
l The independent review shall be documented by the signature of the reviewer i and a brief statement of the general nature of the review (for example, what i was looked at, references used, whether.the procedure was tried in the fiel d). Independent technical reviews of subsequent revisions will be i
required only if the technical nature of the procedure is changed. The normal biennial review of a procedure is, in itself, an independent review and should 1 serve' as such unless major changes are made to the procedure. The independent
! review will not be perfomed for minor editorial changes. The appropriate i department head shall detemine whether an independent technical review is
! necessa ry. The independent technical review will be documented on the i procedure history fom, which is attached to the affected procedure when presented for Plant Staff Review Committee (PSRC) review. During the procedure review by the PSRC, the procedure sponsor will delineate any substantive changes to the procedure to the members of the Committee. ,
Additionally, the Plant Manager has advised the members of the PSRC to review l procedures on the Committee agenda prior to the meeting. !
- The enhanced procedure review process will apply to those referenced i i
procedures that are important to safety, important to environmental quality, or security related.
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r-During Unit 1 low power testing, senior management personnel were temporarily assigned to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> rotating shifts in the control room to provide assistance as needed. They monitored the pace of operations, ensured the control room was not overcrowded, and recorded pertinent observations. Recommendations related to improvements in plant operations were provided to the Plant Superintendent and the Plant Manager.
In order to assure that procedures are adequate and consistent with regulatory requirements and that operators are fully aware and cognizant of regulatory requirements, the following discussions have occurred:
The Plant Superintendent met individually with operators to discuss adherence to procedures and the necessity to evaluate procedures to ensure that they are correct and adequate to accomplish the intended operation.
- Discussions were held with operations personnel to emphasize the necessity to generally slow down the pace of activities and pay particular attention to all operations involving safety-related equipment.
- Licensed operators attended a refresher training session on Technical
- Specifications requirements.
e CORRECTIVE STEPS WHICH WILL BE TAKEN D
A cross reference document correlating plant equipment with technical specification requirements is being developed. The intent is to provide a quickly accessible data base for use by plant personnel to determine all
- r N technical specification requirements related to specific equipment.
-DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance with all technical specification requirements was achieved on
- April 7,1984 with the reclosing of the BIT isolation valve circuit breakers.
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1228d/0016K