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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212B1681999-09-13013 September 1999 Forwards Insp Repts 50-275/99-12 & 50-323/99-12 on 990711- 08-21.Four Violations Being Treated as Noncited Violations ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H6181999-07-27027 July 1999 Forwards Insp Repts 50-275/99-07 & 50-323/99-07 on 990503- 0714.Apparent Violations Being Considered for Escalated Enforcement Action ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot IR 05000275/19980121999-01-13013 January 1999 Informs That Insp Repts 50-275/98-12 & 50-323/98-12 Have Been Canceled DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld ML20195G5161998-11-16016 November 1998 Forwards Insp Repts 50-275/98-16 & 50-323/98-16 on 980913- 1024.No Violations Noted ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236T2931998-07-24024 July 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities for 5 Yrs.Order Being Issued Due to Falsification of Info on Application to Obtain Unescorted Access to PG&E Plant ML20236T3431998-07-22022 July 1998 Forwards Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.Apparent Violations Identified & Being Considered for Escalated Enforcement Action ML20236J2251998-07-0101 July 1998 Ltr Contract,Task Order 232 Entitled, Review of Callaway, Comanche,Diablo Canyon & Wolf Creek Applications for Conversion to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 IR 05000275/19980051998-04-17017 April 1998 Forwards Insp Repts 50-275/98-05 & 50-323/98-05 on 980202-06 & 23-27 & 0302-18.No Violations Noted.Insp Focused on Resolution of Previous NRC Insp Findings & Included Review of Issues Identified During Architect/Engineering Insp Rept ML20203G0371998-02-25025 February 1998 Forwards Revised Copy of NRC Form 398, Personal Qualification Statement - Licensee, (10/97) Encl 1,which Has Been Revised to Reflect Current Operator Licensing Policy DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld ML20199H6691998-02-0202 February 1998 Ack Receipt of ,Transmitting Rev 18,change 11, to Plant Physical Security Plan,Submitted Under Provisions of 10CFR50.54(p).Role of Video Capture Audible Alarm Sys Needs to Be Addressed in Security Plan,Per 980123 Telcon DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld IR 05000275/19970181997-10-31031 October 1997 Forwards Insp Repts 50-275/97-18 & 50-323/97-18 on 971006- 10.Insp Verified That Liquid & Gaseous Radioactive Waste Effluent Mgt Program Was Properly Implemented.No Violations Noted DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML20134H6271997-02-10010 February 1997 Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5) ML20134K3421997-02-0606 February 1997 Conveys Results & Conclusions of Operational Safeguards Response Evaluation Conducted by NRR at Plant,Units 1 & 2, on 960909-12.W/o Encl ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) ML20129J4001996-10-18018 October 1996 Forwards Order Approving Corporate Restructuring by Establishment of Holding Company & Safety Evaluation NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl ML20129G6121996-09-24024 September 1996 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App C,E,F & G.Documents Available in Pdr.App E,F & G Documents Partially Withheld Ref FOIA Exemptions 4 & 6.App D Record Listed as Copyright DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld 1999-09-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 DCL-98-014, Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld1998-02-10010 February 1998 Forwards Change 12 to Rev 18 to Physical Security Plan,Per 10CFR50.54(p).Plan Withheld DCL-97-187, Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld1997-11-19019 November 1997 Forwards Change 11,rev 18 to Physical Security Plan.Encl 1 Describes Proposed Revs to Physical Security Plan.Plan Withheld DCL-97-156, Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld1997-09-16016 September 1997 Provides Change 10 to Rev 18 of Physcial Security Plan & Change 2 to Rev 3 of Safeguards Contingency Plan.Plans Withheld ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML16343A4801997-02-25025 February 1997 Forwards non-proprietary WCAP-14796 & Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. Proprietary Rept Withheld,Per 10CFR2.90 ML16342D5291997-01-31031 January 1997 Transmits WCAPs Supporting NRCs Review of License Amend Request 96-10,rev of TSs to Support Extended Fuel Cycles to 24 months.WCAP-11082,rev 5,WCAP-11594,rev 2 & WCAP-14646,rev 1 Withheld ML16342D5321997-01-24024 January 1997 Requests WCAP-11082,rev 5, Westinghouse Setpoint Methodology for Protection Sys,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1996 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5331997-01-24024 January 1997 Requests Proprietary Version of WCAP-14646,rev 1, Instrumentation Calibration & Drift Evaluation for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation, Jan 1997 Be Withheld from Public Disclosure Per 10CFR2.790 ML16342D5311997-01-24024 January 1997 Requests That WCAP-11594,rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology,Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation Be Withheld from Public Disclosure,Per 10CFR2.790 ML20136C3521997-01-11011 January 1997 Discusses Japan Oil Spill & Np Intake & Possibilities of Such Event Occurring at SONGS or Dcnpp ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses ML16342D5521996-12-18018 December 1996 Requests That Proprietary WCAP-14795, Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methology, Be Withheld (Ref 10CFR2.790(b)(4)) NSD-NRC-96-4846, Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl1996-10-16016 October 1996 Transmits Proprietary & non-proprietary Versions of Preliminary Rept, Incomplete Rcca Insertion. W Authorization ltr,AW-96-1021 & Affidavit Requesting Info Be Withheld from Public Disclosure Encl DCL-96-170, Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld1996-08-14014 August 1996 Forwards Change 1 to Rev 4 of Training & Qualification Plan, Per 10CFR50.54(p).Plan Withheld DCL-96-141, Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld1996-07-31031 July 1996 Submits Change 9 to Rev 18 of Physical Security Plan.Plan Withheld ML20116B8411996-07-22022 July 1996 Forwards Revisions to SR 95-03,SR 95-04 & SR 95-05 Re EDG 1-2 Valid Failures ML20117E6171996-05-24024 May 1996 Forwards Public Version of Rev 11 to EPIP EP R-7, Off-Site Transportation Accidents DCL-96-102, Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld1996-05-0606 May 1996 Submits Change 8 to Rev 18 of Physical Security Plan,Per 10CFR50.54(p).Encl Withheld DCL-96-096, Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 151996-04-16016 April 1996 Forwards Public Version of Rev 3 to Diablo Canyon Power Plant Units 1 & 2 Emergency Plan, Change 15 DCL-96-054, Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld1996-02-28028 February 1996 Forwards Change 7 to Rev 18 of Physical Security Plan & Change 1 to Rev 3 of Safeguards Contingency Plan.Encl Withheld ML20100L4631996-02-23023 February 1996 Forwards Response to NRC Enforcement Action 95-279 Re Violations Noted in Insp Repts 50-275/95-17 & 50-323/95-17 on 951021-1208.Corrective Actions:Directive Was Issued to Plan 2R7 W/Six Day Work Schedule DCL-96-036, Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr1996-02-20020 February 1996 Forwards Public Version of Rev 18 to EPIP EP EF-1, Activation & Operation of Technical Support Ctr ML20097E9341996-01-25025 January 1996 Forwards Public Version of EPIP Update for Diablo Canyon Power Plant,Units 1 & 2 DCL-95-272, Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training1995-12-11011 December 1995 Supports Comments Submitted by NEI Re Licensee Qualification for Performing Safety Analyses,With Listed Exception.Nrc Should Allow Traning Requirement to Be Met by on-job Training DCL-95-264, Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5))1995-12-0606 December 1995 Forwards Change 6 to Rev 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.55(d)(5)) ML20094M6001995-11-21021 November 1995 Forwards Final Rept of Investigation & Analysis of Event 29257 Re Substandard Fastner Processed & Sold by Cardinal Industrial Products,Lp,So That Customers Can Evaluate Situation in Light of 10CFR21.21(a)(1)(ii) & (b)(1) DCL-95-204, Forwards Proposed Changes to Physical Security Plan.Encl Withheld1995-09-19019 September 1995 Forwards Proposed Changes to Physical Security Plan.Encl Withheld DCL-95-199, Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan1995-09-14014 September 1995 Requests Exemption to 10CFR73.55 & Provides Draft Changes to Plant Physical Security Plan ML20087A0471995-07-28028 July 1995 Forwards Security Safeguards Info in Form of Change to Proposed Draft Plant Security Program.Encl Withheld DCL-95-153, Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo1995-07-27027 July 1995 Forwards Public Files Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 14 to 1.1,Rev 8 to 1.2,Rev 11 to 2.1,Rev 5 to 3.1,Rev 12 to 3.2,Rev 6 to 3.5,Rev 14 to 4.3.W/950807 Release Memo DCL-95-134, Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d)1995-07-0505 July 1995 Forwards Rev 4 of Diablo Canyon Security Force Training & Qualification Plan.Encl Withheld Per 10CFR2.790(d) ML20086H5461995-06-29029 June 1995 Forwards Final Exercise Rept for 931020,full Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response plans,site-specific to Plant.No Deficiencies Noted DCL-95-046, Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld1995-02-28028 February 1995 Submits Summary Description of Proposed Vehicle Control Measures Per 10CFR73.55.Encl Withheld DCL-95-039, Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo1995-02-23023 February 1995 Forwards Public Version of Revised Epips,Including EPIP Table of Contents,Rev 18 to EP G-2,rev 3 to EP OR-3,rev 17 to EP EF-1 & Rev 3 to EP EF-9.W/950306 Release Memo ML18101A5671995-02-17017 February 1995 Informs of Improper Presentation of Jet Expansion Model in Bechtel Technical rept,BN-TOP-2,Rev 2 Design for Pipe Break Effects Issued May 1974.NRC May Need to Consider Evaluating Consequences of Potential Misapplication of Expansion Model ML18101A5681995-02-17017 February 1995 Requests NRC to Clarify Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 LCO Under Circumstances as Ref in in 95-10.Subj in Re Postulated Slb W/Potential to Render One Train of Ssps Inoperable ML18101A5741995-02-17017 February 1995 Requests Clarification of Whether Plant Should Declare ESF Portion of Ssps Inoperable & Enter TS 3.0.3 Limiting Conditions for Operation Under Circumstances Described in Info Notice 95-10 DCL-95-033, Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures1995-02-13013 February 1995 Forwards Public Version of Rev 3,Change 14 to Corporate Emergency Response Plan (Cerp) & Cerp Implementing Procedures DCL-95-013, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo1995-01-24024 January 1995 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-11,rev 7A to EP RB-15:F,rev 4A to EP RB-15:G,rev 15A to EP EF-2 & Rev 14D to EP G-4.W/950208 Release Memo DCL-94-258, Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B1994-11-21021 November 1994 Forwards Public Version of Revised Epips,Including Rev 11A to EP RB-8,Rev 4B to EP RB-10,Rev 5 to EP RB-12,on-spot Change to Rev 9 to EP RB-15:C,Rev 16A to EP EF-1 & Rev 3B to EP EF-3B 1999-06-25
[Table view] Category:UTILITY TO NRC
MONTHYEARDCL-90-202, Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.91990-08-0707 August 1990 Forwards Public Version of Corporate Emergency Response Plan Implementing Procedures (Ip),Including Rev 7 to IP 2.2,Rev 4 to IP 3.6,Rev 10 to IP 4.3 & Rev 8 to IP 4.9 ML20043A4131990-05-17017 May 1990 Forwards Response to Violations Noted in Insp Repts 50-275/90-02 & 50-323/90-02 Re Unauthorized Individuals Gaining Access to Vital Areas & Failure to Protect Safeguards Matl.Response Withheld ML20042G6491990-05-10010 May 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML16341F6901990-04-26026 April 1990 Forwards Public Version of Rev 9 to Corporate Emergency Response Plan 4.3, Radiological Analyses & Protection. ML17083C2491990-04-0202 April 1990 Forwards Response to Questions on Geology/Seismology/ Geophysics/Tectonics in long-term Seismic Program Final Rept.Proprietary Data Withheld (Ref 10CFR2.790).W/one Oversize Drawing ML20012E2261990-03-26026 March 1990 Forwards Rev 17 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21) ML20042H0421990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F6431990-03-20020 March 1990 Forwards Public Version of Rev 8 to Corporate Emergency Response Plan Implementing Procedure 4.3, Radiological Analysis & Protection. ML16341F5941990-02-14014 February 1990 Forwards Public Version of Rev 11 to EPIP EP G-4, Personnel Accountability & Assembly. W/900305 Release Memo ML16341F5581990-02-0606 February 1990 Forwards Proprietary WCAP-12495 & Nonproprietary WCAP-12496, Review of Flow Peaking & Tube Fatigue in Diablo Canyon Units 1 & 2 Steam Generators Per El Murphy Aug 1989 Request ML16341F5401990-01-30030 January 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EP M-1 & EP M-6 & Rev 13 to EP G-2S1.W/900215 Release Memo ML16341F5421990-01-29029 January 1990 Forwards Public Version of Rev 7 to Corporate Erpip Update ML20005G0521990-01-0909 January 1990 Forwards Rev 3 to Safeguards Contingency Plan,Per Generic Ltr 89-07.Rev Withheld (Ref 10CFR73.21) ML16341F4351989-11-13013 November 1989 Forwards Public Version of Epips,Consisting of Pages 15,29 & Test Data Sheets to Rev 10 to EP M-4, Earthquake, & Pages 32-1 & 32-3 to Rev 16 to EP M-6, Nonradiological Fire. W/891205 Release Memo ML20246E6061989-08-16016 August 1989 Forwards Endorsements 10 & 11 to Nelia Certificate N-74 & Maelu Certificate M-74 & Endorsements 7 & 8 to Nelia Certificate N-76 & Maelu Certificate M-76,respectively DCL-89-201, Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form1989-07-28028 July 1989 Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form DCL-89-183, Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1989-07-0606 July 1989 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) DCL-89-149, Requests Renewal of Approval of QA Programs for Radioactive Matl Packages1989-05-30030 May 1989 Requests Renewal of Approval of QA Programs for Radioactive Matl Packages ML20244B4881989-04-0707 April 1989 Forwards Endorsement 35 to Maelu Policy MF-103 & Endorsements 65 & 116 to Nelia Policies NF-228 & NF-113, Respectively DCL-89-051, Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo1989-03-0202 March 1989 Forwards Public Version of Rev 5 to EPIP EP R-3 & Rev 10 to EP G-4.W/undtd Release Memo DCL-89-042, Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21)1989-02-23023 February 1989 Forwards Rev 16 to Physical Security Plan,Per NRC .Rev Withheld (Ref 10CFR73.21) ML20235J2191989-02-17017 February 1989 Forwards Endorsements,Including Endorsement 3 to Nelia Certificate NW-132,Endorsement 3 to Maelu Certificate MW-73, Endorsement 4 to Nelia Certificate NW-51 & Endorsement 4 to Maelu Certificate MW-135 ML16341E8821988-11-30030 November 1988 Forwards Proprietary WCAP-12064, Diablo Canyon 1 & 2 Evaluation for Tube Vibration Induced Fatigue. All Five Tubes Requiring Corrective Action Removed from Svc During Unit 2 Refueling Outage.Rept Withheld (Ref 10CFR2.790) DCL-88-277, Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope1988-11-18018 November 1988 Endorses NUMARC Comments on Proposed Rule 10CFR26 Re Fitness for Duty.Receipt of Matl Should Be Ack on Ltr & Returned in Encl Envelope DCL-88-216, Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support1988-09-0202 September 1988 Forwards Public Version of Emergency Response Plan Implementing Procedures for Plants,Including IP 4.5, Engineering & Technical Support ML16342B4691988-08-0101 August 1988 Forwards Proprietary WCAP-11312, Westinghouse Owners Group Tech Spec Subcommittee Reactor Trip Breaker Maint/ Surveillance Optimization Program. Rept Withheld (Ref 10CFR2.790) DCL-88-128, Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21)1988-05-12012 May 1988 Forwards Response to NRC Re Violations Noted in Insp Rept 50-275/88-05.Response Withheld (Ref 10CFR73.21) DCL-88-095, Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21)1988-04-19019 April 1988 Forwards Changes to Rev 16 of Physical Security Plan & Rev 2 to Training & Qualification Plan.Changes Withheld (Ref 10CFR73.21) DCL-88-051, Forwards Rev 16 to Physical Security Plan.Rev Withheld1988-03-0404 March 1988 Forwards Rev 16 to Physical Security Plan.Rev Withheld ML20151G1181988-02-22022 February 1988 FOIA Request for Documents Re ACRS Subcommittee Meetings on 750218-19 Re Plant ML20147E3651988-02-10010 February 1988 FOIA Request for Documents Re NRC 750318 Summary of ACRS Subcommittee Meeting on 750218-19 DCL-87-269, Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21)1987-11-0909 November 1987 Forwards Description of Implementation Schedule for Miscellaneous Amends & Revised Pages for Rev 16 to Physical Security Plan & for Rev 2 to Contingency Plan,Per NRC 870924 Request.Schedule & Revised Pages Withheld (Ref 10CFR73.21) ML20236N5361987-11-0909 November 1987 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments 860323-870322. Rept Same as Reporting Interval of Annual FSAR Update Rev ML20236H9691987-10-26026 October 1987 Forwards Endorsement 25 to Maelu Policy MF-103 & Endorsement 55 to Nelia Policy NF-228 DCL-87-249, Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util1987-10-13013 October 1987 Forwards Page Changes for Rev 16 to Physical Security Plan, Per Util 870826 Commitment in Response to NRC Reaffirming Validity of Violation Opposed in Util DCL-87-216, Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation1987-09-0808 September 1987 Responds to NRC Re Violations Noted in Insp Rept 50-323/87-18.Corrective Actions:Procedure OP A-2:II Revised & Reissued to Clarify RCS Level to Be Maintained During mid-loop Operation DCL-87-202, Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo1987-08-13013 August 1987 Forwards Public Version of Revised Corporate Emergency Response Plan Implementing Procedures,Including Rev 6 to 1.1, Activation of Corporate Emergency Response Organization & Rev 4 to 1.2.W/870826 Release Memo DCL-87-159, Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21)1987-06-30030 June 1987 Forwards Safeguards Info Re Changes to Physical Security Plan,Per 10CFR50.54(p).Encls Include Descriptions of Changes in Rev 15,made Per Amends to 10CFR73.55 & Changes in Rev 16. Rev 16 Also Encl.Encls Withheld (Ref 10CFR73.21) DCL-87-146, Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21)1987-06-25025 June 1987 Forwards Proprietary Response to Violations Noted in Insp Repts 50-275/87-19 & 50-323/87-19 Dtd 870529.Response Withheld (Ref 10CFR73.21) DCL-87-129, Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-11987-06-0808 June 1987 Responds to Generic Ltr 87-06 Re Verification of Leaktight Integrity of Pressure Isolation Valves.License Amend Request 86-01 Submitted on 860213.To Date,License Amend Not Received to Add Valves to Table 3.4-1 ST-HL-AE-2035, Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl1987-04-30030 April 1987 Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl ML20207R4571987-03-13013 March 1987 Forwards Endorsements 52 & 110 to Nelia Policies NF-228 & NF-113,respectively DCL-87-045, Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised1987-03-11011 March 1987 Responds to Violations Noted in Insp Rept 50-275/87-06 Dtd 870210.Corrective Actions:Investigation Begun,Including Review of Actions Taken & Documentation & Discussions W/Util Personnel,State & County.Emergency Procedure G-3 Revised DCL-87-042, Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-0031987-03-0909 March 1987 Forwards Rept Providing Verification of Completion of Requested Program,Summary of Valve Operability Prior to Adjustment & Valve Data in Tabular Form,Per Item F of IE Bulletin 85-003 DCL-87-041, Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21)1987-03-0505 March 1987 Forwards Response to Safeguards Violations Noted in Insp Rept 50-275/87-02.Response to Paragraphs 2.D & 10 of Rept Provided in Encl 2.Encls Withheld (Ref 10CFR73.21) 05000275/LER-1985-014, Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip1987-03-0303 March 1987 Forwards LER 85-014-02 Re Reactor Trip & Safety Injection. Rev Repts Discovery of Addl Damaged Snubber Resulting from Water Hammer After Reactor Trip DCL-87-024, Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-271987-02-12012 February 1987 Forwards Public Version of on-the-spot Procedure Change to Rev 9 to Emergency Plan Implementing Procedure EP G-3, Notification of Offsite Organizations, Per Generic Ltr 81-27 ML20211F5121987-02-11011 February 1987 Informs That Lt Gesinsky Has Become Seriously Ill & Will Not Be Able to Testify,As Witness,On Behalf of Util.Ee Demario Will Replace Lt Gesinsky as Witness.Prof Qualifications Encl DCL-87-014, Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage1987-01-28028 January 1987 Forwards Response to Rev 2 to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Cracking or Other Unacceptable ASME Code Discontinuities Identified in Volumetric Insp Performed During First Refueling Outage DCL-87-006, Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler1987-01-12012 January 1987 Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler 1990-08-07
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PACIFIC GAS AND E LE C T RIC C O M PANY 77 BEALE STREET, SAN FR ANCISCO, C A LIFORNI A 94106 TELEPHONE (415) 781 4211 April 4, 1984 PGandE Letter No.: DCL-84-130 Mr. John B. Martin, Regional Administrator U. S. Nuclear Regulatory Commission, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-76 Diablo Canyon Unit 1 Response to IEIR 83-41 -- Notice of Violation
Dear Mr. Martin:
NRC Inspection Report 50-275/83-41, dated March 5, 1984, included three Severity Level IV violations and one Severity Level V violation. PGandE's response to this Notice of Violation is enclosed.
Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely, W. A. Raymond for J. O. Schuyler Enclosure cc: Service List l ' .. ;%6 l
'l i ;ll ni a - g i g a 8405040145 840426 PDR ADOCK 03000275 O PDR 00W G3M7CJ!!
PGandE Letter No.: DCL-84-130
- ENCLOSURE RESPONSE TO NOTICE OF VIOLATION NRC INSPECTION REPORT 50-275/83-41 On March 5, 1984, NRC Region V issued three Severity Level IV and one Severity Level V Notices of Violation as part of NRC Inspection Report 50-275/83-41 for Diablo Canyon Unit 1. The notices cited:
e A concern that the mechanical bypass, jumper and lifted circuit log was improperly filled out.
e A concern that welding activities were being conducted with improper fire prevention controls, e A concern that the Solid State Protection System (SSPS) was removed from service without written procedures, e A concern that the containment equipment door was not fully closed during core alterations (initial fuel load).
The inspection report also mentioned a concern by the NRC that schedule pressures, hurried atmosphere of work activities and extensive overtime may be a contributing cause of these observed discrepancies.
PGandE has recognized that the naturally occurring emphasis on the plant completion effort can lead to degraded personnel performance. In order to preclude this from happening as Diablo Canyon approaches initial operation, management actions have been undertaken in several areas.
One example of such action is the issuance of a letter from the Plant Manager in December 1983 to all Diablo Canyon Managers and Supervisors emphasizing that "The single most important thing at Diablo Canyon is quality of plant work activities," " Employees must never let schedule pressures or other considerations influence performance of a safe and quality job", "
.. .take the necessary time to do the job right the first time", and " Procedures should not be violated, nor should an incorrect procedure be followed...". Another example is the special meeting of the Plant Staff Review Committee (PSRC) which convened on December 6,1983, in order that senior plant management cculd assess the possible effects of schedule pressurer, on performance and consider steps which could be taken to maintain performance. '
Management measures received additional implementation in late February and early March of 1984 when the Plant Manager and his senior staff reviewed the impact of schedule pressures on the groups performing the most overtime work.
Further, because it was concluded that continuation through low power testing of the level of overtime worked in some groups, without relief, might cause performance degradation, a general standown from overtime was required during I
073Gd/0009K March. This action was taken despite any effect on schedule, for the maximum possible number of people.
This relief, coupled with the completion of most of the " outage-intensive" work by the I&C Department (the most affected plant department), assures that the Diablo Canyon work force is able to continue its efforts in an alert and able manner.
A. JUMPER LOG'WAS FILLED OUT IMPROPERLY STATEMENT OF VIOLATION
[ Technical Specification 6.8.1 stated that " Written procedures shall be
- established, implemented and maintained coverning... applicable procedures recommended in Appendix 'A' of Regulatory Guide 1.33, Revision 2, February 1978. Appendix A Item 1.j. " Bypass of Safety Functions and Jumper Control" is implemented by the licensee's Nuclear Plant Administrative Procedures (NPAPs) C-4 and C-4 Sl. NPAP C-4Sl, (Item 3.9.7), requires that any bypass of safety functions must be indicated on the Mechanical Bypass, Jumper and Lifted Circuit Log (jumper log).
j Contrary to the above, jumper log number 83-190, 191, 193 and 194 indicated on July 30 and August 1, 2 and 3 respectively that the safety
, function of the pressurizer pressure transmitters had not been bypassed, even though the safety function was indeed bypassed.
This is a Severity Level V Violation (Supplement 1).]
STATEMENT OF EXPLANATION The event was the result of belief that a Safety Function Bypass was not required, since the operability (including the effect of the jumper on the equipment) is typically verified when the equipment is returned to service.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- 1. The Plant Staff Review Committee (PSRC) approved the bypass consisting of a jumper on the pressurizer pressure instrument on December 19, 1983.
- 2. The Operations Manager had discussed the importance of proper jumper log documentation with operation department supervisors, emphasizing the definition of the Safety Function Bypass.
, 3. The Operations Manager issued Shift Foreman memo 83-95 to emphasize that the Bypass of a Safety Function is not dependent upon the operating mode and must always be addressed.
- 4. The Operations Manager has required additional training of operators be immediately instituted on Administrative Procedures NPAP C-4 and C-4S1 emphasizing Bypass of Safety Functions.
- 5. Administrative Procedure NPAP C-4 and C-451 have been revised and approved by the Plant Staff Review Committee on March 15, 1984. The revisions clarify the requirements concerning. jumpers and Bypass of I Safety Functions.
t :
0736d/0009K -_. ._ _
l CORRECTIVE STEPS WHICH WILL BE TAKEN Based on the actions described above, PGandE believes that adequate corrective actions have been taken to prevent recurrence. Therefore, no additional corrective steps are necessary.
_DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on April 3,1984.
B. WELDING ACTIVITIES WERE BEING CONDUCTED WITH IMPROPER CONTROLS STATEMENT OF VIOLATION
[ Technical Specifications Section 6.8.1.f, " Procedures and Programs,"
specifies that written procedures shall be established, implemented and maintained for a Fire Protection Program. PGandE Nuclear Administrative Procedure (NPAP) C-13 Rev. 3, " Fire Loss Prevention," Item III.B 6.a specifies that "... combustible material...in the work area shall either be removed or protected by approved fire retardent material below and within a 35 foot radius circle of the work site." NPAP C-13, Rev. 3, Item III.B.6.d also specifies that "... suitable fire extinguishers shall be readily accessible to the area while the job is in progress and until the fire watch is completed."
PGandE NPAP C-13 S1, Rev. 1, " Supplement to NPAP Diablo Canyon Welding and Open Flame Permit," Item 3.e also specifies that "...the Welding Foreman is to assure that workers and fire watches are complying with the requirements of the applicable ' Welding and Open Flame Permit'"
NPAP C-13 S1, Rev. 1. Item A.e also specifies that " prior to the start of the actual welding or open flame work, the worker or the fire watch will initial the right side of the form after each of the requirements designated by the ' Welding Foreman' has been accomplished."
Contrary to the above requirements, on December 19, 1983, welding operations were being conducted near motor generator set No. 2 with combustible material nearby, no fire extinguisher or fire watch present and with no initials appearing on the welding and open flame permit.
This is a Severity Level IV Violation (Supplement 1).]
EXPLANATION AND CORRECTIVE STEPS TAKEN The plant administrative procedures require that work involving welding or the use of an open flame be controlled. Specific fire protection requirements are designated by the " welding foreman" and are to be implemented by the worker and the fire watch.
It has been determined that the training of " welding foremen", workers, and fire watch personnel did not sufficiently address the Welding and Open Flame Permit system. This resulted in the workers and the fire watch not implementing the requirements of the Welding Permit.
The welding activity was stopped immediately on December 19, 1983, when the resident inspector notified the plant Fire Marshal of the situation. l The Welding Permit was also cancelled immediately. Work was not allowed 0736d/0009K l
I to resume until the area was cleared of combustible materials and the
- involved personnel were instructed in their responsibilities. Work recommenced following an inspection of the work area by the Fire Marshal ,
and issuance of a new Permit. l The plant Fire Marshal's office was augmented as of January 1984 with additional contract and Project personnel assigned to assist construction
" Welding Foremen" with the completion of Welding and Open Flame Permits.
These personnel also monitor work activities to assure that permit ,
requirements are being implemented.
The December 19th event strongly contributed to the decision in late l
January 1984 to require project and contractor personnel to participate in training sessions covering work rules in Unit 1. These sessions were given on a rotating basis, covering all such personnel within a 2 week period. The Fire Protection program and the welding and open flame permit requirements were strongly emphasized during this training. The Fire Protection portion of the training program was conducted in multiple sessions by the Project Fire Marshal and was completed on February 3, 1984. Additionally, fire watch training sessions were completed on January 6, 1984 and again on February 7, 1984, which emphasize the importance of Welding Permits and the conduct of safe welding operations.
A training session emphasizing Welding Permits was conducted for NPO Maintenance personnel on January 30, 1984, by the plant Fire Marshal.
CORRECTIVE STEPS WHICH WILL BE TAKEN Based on the actions described above, PGandE believes that adequate corrective actions have been taken. Therefore, no additional corrective steps are necessary.
DATE_WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on February 7, 1984.
C. THE SOLID STATE PROTECTION SYSTEM (SSPS) WAS REMOVED FROM SERVICE WITHOUT H ITTEN PROCELURES STATEMENT OF VIOLATI(M
[ Technical Specification 6.8.1 states that " Written procedures shall be established, implemented and maintained covering... applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Rev. 2, February 1978." This regulatory guide required procedures for performing maintenance. Sptcifically, this guide requires procedures for
... Maintenance that can affect the performance of safety-related equipment..."
, Contrary to the above, on December 7, 1983, in order to perform surveillance activities on the Solid State Protection System (SSPS), the :
licensee removed the SSPS from service without first establishing written procedures for the removal of the SSPS.
This is a Severity Level IV Violation (Supplement I).] ,
l l
0736d/0009K I
I I
STATEliENT OF EXPLANATION The Notice cites a concern that the SSPS was removed from service without first establishing written procedures. Step 1 of Surveillance Test Procedure STP l-16C is the " REMOVAL FROM SERVICE" section of this i procedure. In addition, Temporary Procedure TP-8307 covered the lifting l of leads TB-607-9 and TB-607-11 in the SSPS to prevent loss of high voltage to the nuclear source range instrumentation. A Shopwork Follower was used to tie these two procedures together. Though written procedures were established and the proper steps were specified, the temporary procedure and shopwork follower were inadequately labeled, resulting in a misunderstanding as to the proper time to lift the leads to prevent the loss of high voltage to the nuclear source range instrumentation.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- 1. The high voltage to the nuclear source range instrumentation was restored in approximately two minutes after it was deenergized.
- 2. Surveillance Test Procedure STP 1-16C has been revised to ensure that leads are lifted and reterminated in a proper manner. This revision i eliminates the need for two procedures and reduces confusion.
- 3. A training session was conducted for I&C Supervision and covered the following points:
- a. The necessity to conduct training meetings on unfamiliar or non-routine evolutions.
- b. The importance of performing a job safely, correctly and in accordance with requirements is the number one priority regardless of the schedule.
- c. The responsibility of supervision is to ensure that technicians-understand the importance of consulting with their supervisor if they don't fully understand their assignment.
- 4. Senior I&C Supervision conducted a training session for all I&C personnel to emphasize the importance of communicating with supervision when work assignments are not fully understood.
- 5. This item was reviewed subsequently in an " Incident Review Board" with NRC participation. Essentially the same conclusions were reached. The review board did suggest preparation and dissemination of a short written summary of any similar future event soon after the occurrence in order to preclude its repetition.
CORRECTIVE STEPS WHICH WILL BE TAKEN Based on the actions described above, PGandE believes that adequate corrective actions have been taken to prevent recurrence. Therefore, no additional corrective steps are necessary.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on December 23, 1983.
1 0736d/0009K 9
1
. 1 D. THE CONTAIN!!ENT EQUIPMENT DOOR WAS NOT FULLY CLOSED DURING CORE
. AEITRATION5 1
STATEftENT OF VIOLATION 1
[ Technical Specification 3.9.4 requires that "...the equipment door (shall be) closed...during core alterations..." and "...with the requirements of the above specifications not satisfied, immediately suspend all operations involving core alterations..."
Contrary to the above, on November 29, 1983, a gap of greater than one inch existed between the top of the equipment hatch and its mating i
surface on the containment. The equipment hatch was fastened in position with four bolts below the equipment hatch centerline. The licensee had previously performed core alterations during the period November 15 to November 20, 1983 (initial fuel load).
This is a Severity Level IV Violation (Supplement I).]
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED Maintenance Procedure MPM-22, concerning the equipment door, was revised to give explicit instructions for Mode 6 (refueling), equipment door closure requirements. The revised procedure now requires a gap inspection to verify adequate door closure in Mode 6.
After fuel load, the equipment door was removed for maintenance purposes in Mode 5 (cold shutdown). Currently, the equipment door is installed with a full compliment of closure bolts and has been leak tested.
CORRECTIVE STEPS WHICH WILL BE TAKEN Based on the action described above, PGandE believes that adequate corrective action has been taken to prevent recurrence. Therefore, no additional corrective steps are necessary DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED .
Full compliance was achieved by February 20, 1984.
i 0736d/0009K _