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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 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 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)) 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:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML19327A8691989-09-0707 September 1989 Submits Info Re Alchemie & Anderson County Bank Financing Transaction ML19332F2171989-07-10010 July 1989 FOIA Request for Documents Re Communications Between Ofcs of Edo,Deputy Edo,Ofc of Director,Regional Administrators & Commissioners Ofcs Re Plants During period,890301-0615 ML20246F1311989-06-26026 June 1989 FOIA Request for Minutes of Meeting Ref in 820210 Memo from NRR Re Design & Const Assurance for Upcoming OL Cases ML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20245C1421989-04-0303 April 1989 Forwards Endorsements 75,108,108,96 & 110 to Maelu Policies MF-56,MF-26,MF-58,MF-39 & MF-52,respectively & Endorsements 93,129,127,109 & 122 to Nelia Policies NF-186,NF-76,NF-188, NF-151 & NF-173,respectively ML20247N1551989-03-31031 March 1989 Forwards Revised Proprietary Conformance of HPCS Div to NUMARC 87-00 Alternate AC Criteria, for Review as Result of Comments from 890216 Meeting.Rept Withheld ML20246M7331989-03-15015 March 1989 Responds to NRC Info Notice 88-082, Torus Shells W/ Corrosion & Degraded Coatings in BWR Containments. Summary of Relevant Projects for Various Utils Successfully Employing Underwater Alternative to Draining Vessel Encl ML20246N1281989-02-27027 February 1989 FOIA Request for Jl Smith to NRC Re Spent Fuel Shipment from Brunswick Nuclear Power Station to Harris Plant ML17285A2351989-02-0606 February 1989 Forwards Proprietary Draft Conformance of HPCS Div to NUMARC 87-00 App B Aac Criteria, for 890214 Meeting ML17285A2341989-01-0606 January 1989 Discusses Issues Highlighted at BWR/6 Alternate Ac Task Force Meeting on 881115,including Need for Capability of Div III Sys to Maintain Plant in Safe Shutdown Condition (Hot Shutdown) for Min of 4 H ML20206H0511988-11-14014 November 1988 Urges Relicensing of Pilgrim & Expedited Operation of Seabrook.Newspaper Clipping Encl ML20150D5721988-03-0808 March 1988 Provides Summary of Utils Test Results & Calculations on Emergency Diesel Generators,Including Review of Design of Static Exciter & Voltage Regulator for Emergency Diesel Generators ML20196C1591988-02-0303 February 1988 Forwards Monthly Progress Rept P-C6177-5, Independent Analysis & Assessment, for Period Ending 880131 ML20147G0741988-01-18018 January 1988 FOIA Request for All Documents Re NRC Investigation of Wg Dick Allegations About S&W & Lilco Re Performing NRC Instructions to Bring Facility Up to Fuel Load Stds ML20150D4301988-01-0707 January 1988 FOIA Request for Records Re 1975 NRC Seismic Design Audit of Facility ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20234D7951987-12-14014 December 1987 FOIA Request for Documents Re Encls to to Util Transmitting Suppl to Safety Evaluation & Environ Assessment ML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20236S4291987-10-20020 October 1987 FOIA Request for Listed Documents,Including Encls from NRC Requesting Addl Info on Gpu Topical Repts TR-033 & TR-040 & Encl to NRC Meeting Summary Re SPDS ML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20235V1321987-08-28028 August 1987 Forwards EGG-NTA-7471, Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28.... Based on Licensee Responses,Plants Reviewed Conform W/Exceptions Listed in Section 14 ML17342A7741987-07-13013 July 1987 Forwards Technical Evaluation of Rept, Retran Code: Transient Analysis Model Qualification, Dtd Jul 1985. Criteria for Use of Single & Two Loop Plant Models Listed. NRC Audit of Util QA Procedure Recommended ML20235K8731987-07-0909 July 1987 Informs That Tayloe Assoc Cannot Produce Mag or nine-track Tapes of Hearing Transcripts Until NRC Finalizes Arrangements W/Others to Provide Lexis Format,Including Library & File Numbers & Segmentation Info ML20235Y1711987-07-0606 July 1987 FOIA Request for Documents Re Investigation Into Plant Seismic Design Error ML20235R9191987-07-0202 July 1987 FOIA Request for Statement of Work on Plant Project Verification & Contracts Awarded to BNL by NRC Through DOE for FY79 - FY85.Scope of Work Only,Not Financial Info, Requested ML20237J2141987-07-0202 July 1987 FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML20234B6211987-05-12012 May 1987 Requests That Listed Plants Be Added to Encl 870508 FOIA Request Re 94300 Region Input on Plant Readiness ML20234B6571987-05-0808 May 1987 FOIA Request for Placement,In Pdr,Region Input to NRC Headquarters,Nrr Re Status of Listed Plants in Terms of Plant Readiness for OL IE Manual,Chapter 94300 ML20214R4051987-05-0808 May 1987 FOIA Request for Region Input to NRR Re Status of Listed Plants Readiness for Ol,Per IE Manual Chapter 94300 ML18150A1861987-05-0101 May 1987 Forwards EGG-NTA-7612, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components,North Anna Units 1 & 2 & Surry Units 1 & 2, Final Informal Rept ML20214R0621987-04-17017 April 1987 Forwards EGG-NTA-7613, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,Arnold, Brunswick-1 & 2, Final Rept.Plants Conform to Item ML20214Q8801987-04-17017 April 1987 Forwards EGG-NTA-7591, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28 Reactor Trip Sys Vendor Interface,Hatch-1 & 2,Millstone-1, Final Rept.Plants Conform to Item ML18150A1171987-04-14014 April 1987 Forwards Final rept,EGG-NTA-7625, Conformance to Item 2.1 (Part 2) Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20237J3401987-04-13013 April 1987 FOIA Request for Transcript of 830106 Meeting W/Individual Re Alleged Deficiencies in Plant Component Cooling Water Sys ML20214R8611987-03-27027 March 1987 Forwards EGG-NTA-7614, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Cook-1 & -2,Haddam Neck, Final Informal Rept.Facilities Conform to Generic Ltr ML20214R1361987-03-26026 March 1987 Forwards Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Maine Yankee, St Lucie 1 &-2 & Waterford 3, Final Rept.Plants Conform to Generic Ltr ML20214R1861987-03-26026 March 1987 Forwards Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components,Haddam Neck & Millstone 1,2 & 3, Final Rept ML20205M4951987-02-20020 February 1987 FOIA Request That All Operational Readiness Ltrs for Diablo Canyon Be Placed in PDR ML20207T1001987-02-13013 February 1987 FOIA Request for Two Categories of Documents Re Diablo Canyon Nuclear Power Plant,Consisting of Transcripts of Closed Commission Briefings on 830422,840131 & 0702 & Secretary 831104 Limited Distribution Memo ML20211D6631987-02-12012 February 1987 Notifies of 830204 Meeting W/Util,Idvp,Nrc & BNL in San Francisco,Ca to Discuss Status of Containment Annulus Steelwork & Status of Auxiliary Bldg ML20211D7031987-02-12012 February 1987 Notifies of 830209 Meeting in San Francisco,Ca to Discuss Shake Table Tests of Electrical Equipment ML20211D7441987-02-12012 February 1987 Notifies of 830517 Meeting in San Francisco,Ca to Discuss Development of Piping Stress Intensification Factor ML20210M9071987-01-26026 January 1987 FOIA Request for Transcript of Commissioner 831017 Briefing Re Diablo Canyon Idvp ML20207T2211987-01-16016 January 1987 FOIA Request for Commissioner 811116 Briefing Transcript Re Diablo Canyon Seismic Design Error & NRC pre-congressional Testimony & Commissioner 811119 Briefing Transcript of NRC pre-congressional Testimony ML20209A8551987-01-16016 January 1987 FOIA Request for Documents to Be Placed in Pdr,Including NRC Re Calibr of Test Equipment allegation,1986 Inservice Insp Repts for McGuire 1 & Surry 1 & NRC 830307 SALP on Nine Mile Point 2 ML20207R6541987-01-0909 January 1987 FOIA Request for All Petitions Referred to Licensing Board by 740319 Memorandum & Order CLI-74-10 & All Licensing Board Orders,Director'S Decisions or Further Commission Orders Responding to Such Petitions ML20207K0151986-12-19019 December 1986 FOIA Request That Encls to Insp Rept 50-247/86-26,Byron Semiannual Radioactive Effluent Rept & Millstone 1 & 2 SALP Rept Be Placed in PDR 1989-09-07
[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 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 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 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 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 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 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 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 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
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- * - %p . ( h ATS No: RV-83A-0073 BN No:
Characterization:
Alleged deficiencies in H. P. Foley welding program including: (1)~the use of unqualified welders; (2) the use of unqualified welding procedure specifications; (3) gross'erros contained in welding procedures including nonconformance with industry codes; and (4) design errors. The nonconformance reports which document the substance of the allegations were prepared by the r
. alleger while an employee of the H. P. Foley Company.
Implied Significance to Plant Design, Construction or Operation:
The H. P. Foley Company performed safety-related welding on: electrical components; heating, ventilation, and air conditioning systems; and -
instrumentation tubing. Improper velding could cause equipment failure and attendant loss of design functions during normal operation or during design basis events, including seismic events.
I r
Assessment of Safety Significance: .
I I
The alleger provided the staff with a listing of wpecific weld procedute l
specifications and quality control procedures and copies of nonconformance reports to support his contentions. The staff approach to resolution of this issue was to examine how the H. P. Foley Company addressed the concerns and i 12.3 4
nonconformance reports issued by the alleger, and to independently assess the quality of the Foley welding program using the specific examples provided by the alleger, supplemented with additional investigation of related areas of
'the welding program.
Th"e alleger's stated concern was that the adequacy of safety-related welding performed by the H. P. Foley Company was indeterminate in that:
(1) Unqualified welders are used.
Staff Note: The alleger's concern regarding welder qualifications was vague and unspecific but appeared, from nonconformance report 8802-924, item 2 as supplied by the alleger, to be directed towards lack of formal l
welder training rather than lack of strict compliance with the.
qualification requirements of the applicable codes.
, (2) .Welding procedures are not adequately qualified. See QCP-5A, welding.
- i. procedure specifications (WPS) 31, 32, 35. 36, and 86 and see comment sheets;for QCP-5A (Rev. 9).
. (3) Welding procedures QCP-5A (Rev. 3, 4, 5 and 9), QCP-5B (Rev. 3 and 4),
QCP-SC (Rev. 0), and QCP-SD (Rev. 0) contain gross errors and are not in accordance with the applicable codes. See NCR-8802-924, for example,
( relative to QCP-5A, Rev. 9.
l (4) As indicated in NCR-8802-924, item 9, there are design errors.
(
The staff investigated the above stated concerns by: (1) conducting a thorough review of procedures specified by the alleger and associated procedures; (2) reviewing past NRC and NRC contractor (EG6G). inspection findings involving Foley weld quality; (3) interviewing, in private, over twenty responsible license and contractor personnel; (4) reviewing over 700 nonconformance .
re" ports issued by H. T. Foley; (5) reviewing qualification records for six welders;'and (6) examining veld quality on over 100 components located in the Unit 1 containment, cable spreading room, turbine building, control room, and 480 volt switchgear rooms.
The staff investigtion of the alleger's concerns found that:
(1) The alleger's assertion that welders were unqualified was not confirmed.
A staff review of qualifications for six welders found them in compliance with applicable codes with the exception of the minor deficiencies discussed below. A previous NRC investigation of Foley welder
. qualifications and procedure QCP-5 for AWS structural welding found that the procedure provides a system for qualifying and maintaining the qualifications of welders which was confirmed by a review of qualification records for seventeen welders (IE Report No. 50-275/83-13).
Further, the staff concludes that the Foley resolution of the alleger's nonconformance report No. 8802-942,- Rev. 2 properly dispositioned the apparent concern regarding inadequate welder training. Two minor-deficiencies were identified b'y the staff during review of this issue:
/
(a) The welder qualification list indicated that welder "US" was qualified to limitation 1 whereas the welder qualification records
indicated that he was qualified to the more restrictive limitation 2.
(b) The qualification record for welder "M27" for limitation 5 does not 11dicate completion of an acceptable fracture test as required by
~
the ASME Code Section IX, Subsection QW-452.4.
a.
(2) No significant deficiencies in the qualifications of QCP-5A procedure Nos. WPS-31, 32, 35, and 36 were identified by the staff. WPS-86 has been deleted from QCP-5A and the staff was informed that-it was never used. The staff concluded that the alleger's concerns over procedure qualifications were properly addressed in nonconformance report No. 8802-924 and associated correspondence. The following minor deficiencies were identified by the staff in the reviews of welding procedure qualifications for procedures contained in~other QCP's:
(a) The'velding procedure qualification rec,ords for QCP-SC, WP-RS-4 do not indicate performance of th'e macroetch test required by the AWS D1.4-79 code.
(b) The welding procedure qualification record for QCP-5D, MOS does not -
list the .ctual preheat used as required by the ASME Code Section IX, Subsection QW-201.
(c) Procedure QCP-5C does not place any restriction on the carbon equivalent of reinforcing steel welded in accordance with a qualified welding procedure as required by the AWS D1.4-79 code.
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. (3) No gross errors were identified in the welding procedures. The procedural concerns described in NCR 8802-924 were dealt with in a letter from the Quality Director to the alleger dated September 29, 1983, in nonconformance report Nos. 8802-942R2, - 938R2, -951, -940R1, and -941,
, and in Engineering Disposition Request Nos. 1337 and 1432. The staff.
~
considers all of the concerns described in NCR 8802-924 to have been satisfactorily addressed by the licensee. A minor deficiency was identified by the staff during the procedure review regarding instructions from PG&E to the H. P. Foley Compaar to weld thin she'et metal to the requirements of the AWS DI.1-75 Code which is not intended for this application.
(4) The staff identified no design error associated with the alleger's.
specific concern. .
Staff Position The review of the alleger's conceres failed to identify significant welding program or hardware deficiencies or any instance in which the alleger's concerns were not addressed properly. The welds observed by the staff in installed components and structures, were judged adequate for their applications. -
The evaluation of the licensee's cohpliance with regulatory requirements and applicable industry codes and standards conducted during the investigation identified some deficiencies. These deficiencies are not considered significant enough to suggest that the integrity of safety-related components
< is in question, however..they must be addressed and satisfactorily resolved by the licensee.
I Action Required:
Ev'aluation of apparent deficiencies by the NRC staff for possible enforcement action and examination of licensee actions to resolve the identified deficiencies. This will be monitored through the routine inspection program.
1
i; PROBLEM STATEMENT Allegation No(s): 101 ATS No(s): RV-83A_0073 BN(s):
This document lists (or directly references) each allegation or concern brought-to the attention of NRC personnel. The purpose of this statement sheet is to assure that ALL points raised by the alleger are covered.
- If the problem statement is not clear as to who, 'what, where, when,- of- why regarding the issue, the commentary section" will amplify the statement. The~ commentary section will also-be used if .there is apparent conflicting information or if there is NO or-very little original information available which describes the concern (s). ( This*can occur if, for example, a one line concern
~
was received in an interview).
PROBLEM STATEMENTS (use extra sheets as necessary)
ALLEGATION #- VERBATIM STATEMENT OR REFEPENCE i 101 Reference Howard P. Foley Company Interor'fice Communication dated 12/2/83 from confidentia' alleger (quality control inspector, to Albert Ruff, HRC. Also see blue binder of backup material provided by the same alleger.
COMMENTARY The referenced communication itemizes t h e u s e ,- in procedure Mo.
QCP-5A, of terms such as "maybe", "should be", "if necessary",
etc., without comment as to why such use is objectionable. This aspect of the original aproblem statement has not been specifically addressed although procedure SA was- reviewed and found satisfactory.
Date This Statement was Completed 3/9/84 . 'i ist Technical Reviewer Signature PROBLEM STATEMENT 5
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Ac7kstfr%ts y Nwoomiams/m -
welder ' training.
Two minoY deficiencies were identified by the staff during review of this issue:
(a) The ' welder qualification list indicated that selder "US" was qualified to limitation 1 whereas the welder qualification records indicated that he was qualified to the more restrictive limitation 2. -
(b) The qualification record for welder "M27" for limitation 5 does not indicate completion of an acceptable fracture test as required by the ASME Code Section IX, Subsection QW-452.4.
correspondence.. The following minor identified deficiencies were by qualifications for the staff in the reviews of procedures welding -procedure contained in other QCP's:
(a)
- The welding procedure qualification records for QCP-5C, WP-RS-4 do not indicate performance of the macroetch test required by the AWS D1.4-79 code.
, (b) The welding procedure qualification record for QCP-SD, MOS does not list the actual preheat used as required by the ASME Code Section IX, Subsection QW-201.
(c) Procedure QCP-SC does not place any restriction on the carbon equivalent of reinforcing steel welded in accordance with 4 qualified welding procedure as required by the AWS D1.4-79 code.
addressed by -the licensee. An apparent minor deficiency wa's identified by the staff during the procedure review regarding instructions .from PG&E to the H.P. Foley Company to weld thin sheet metal to the requirements of the AWS D1.1-75 Code which is not intended for this application.
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- C Fa'm 38 ALLE2ATlHN DATA F3RM u.s. NUCL A3 REGULATORY COMMISSION
' 11NI in.ituction. on ,.. ..o.
RECEIVING OFFICE
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poneric. write GENERIC) f
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- 2. Functional Areals) Involved:
(Check ppropriate boat ): operations _
onsite health and safety construction offsite health and safety
_ safeguards ._ _ emergency preparedness
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Description:
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- 5. Date A!!egation Received:
- 6. Name of individual triest two initi.i and int n mel - IA> -
Receiving Allegation:
- 7. Of fice:
g ACTION OFFICE
- 8. Action Office
Contact:
trirst two initi is and insi n.m.) e ,/
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ATS No. RV-84-A-007 BN No.
Characterization:
Changes from Interim "As Built" Drawings to Final Drawing - Inadequate Control has been exercised over the transition from Interim Drawings to Final Drawings of the station as actually constructed. ~
[n w.Assessment of Safety Significance A face value assessment on the part of the staff indicates this issue is not of major significance in terms of public health and safety or management breakdown. Also, this issue appears to be a restatement of concerns identified and examined in allegation 61. The issue is a known issue and 2s being responsibly handled.
Staff Position The issues of concern here do not appear to represent any new significant management or quality performance issues which have not been previously addressed.
Action Required y g pb4ff This issue will be turned over to PG&E for =~1"* '--
The licensee will be ,
required to provide a written response to their findings and corrective actions.
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I' ' - additional quality control personnel. These personnel were -
certified to a certain level by Cataract based on experience and verified by an investigative service. However, the resumes
, of the individuals, in some cases, did not support the i certifications in some areas. This problem was identified by --
licensee Quality Assurance Audit No. 83043A, performed in February 1983, and further documented on Nonconformance Report No. 8802-824, dated March 17, 1983. Currently the' licensee, ,
the H. P. Foley Company, and Cataract Engineering Company are
- resolving the problem by verifying past employment of the personnel in question. In the interim, personnel with a
- potential resume problem are not being used in the field as
- quality control inspectors. This nonconformance report (NCR l
. No.'8802-024) also notes that between December 7,1982 and .
March 10, 1983, Level I inspection did not require a Level II co-signature, and further notes that, "This nonconformance encompasses both H. P. Foley direct inspection personnel and sub-contracted, Cataract Engineering Company personnel." The 4
resolution of these licensee audit findings will be examined l during a future inspection. (50-275/83-13-01)
No items of noncompliance or deviations were identified.
i e. Concern: The concern was expressed or implied that as a result
< of increased construction activity starting in September 1982 l and the accelerated hiring of craft personnel, welders hired j- during this period might not be properly certified.
NRC Findinas: The specific concern that welders hired since t
September 1982 might not be properly certified was not l substantiated, however an apparent item of noncompliance with welder certification was identified during this examination and
. is detailed below.
. k -
To address this concern the inspectors examined H. P. Foley's
.. Quality Control Procedure for Welder and Brazer Qualifications and the Qualifications,of Welding and Brazing Procedures (QCP-5, Revision 8, dated 1/28/82) and determined that the
. procedure provides a system for qualifying welders and maintaining a continuous record of qualification status of all welders. The procedure references and appears to comply with the latest edition of the AWS D1.1, Structural Welding Code, for documenting test results and describes the steps necessary to qualify a procedure and a welder in accordance with Code requirements. ,
! An' examination of the qualification records for seventeen l welders (ironworkers, pipefitters, and electrical welders) established that all of the welders certified since September 1982 had been properly certified and monitored in accordance with requirements of QCP-5. However, the inspector noted that one electrical welder (symbol "JX"), initially certified on l
February 27, 1980 to an AWS D1.1 Shield Metal Arc Welding (SMAW) Process, had last been monitored by Quality Control on Ck 1 .
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-9 s July 27, 1982. H. P. Foley procedural requirements specify -
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that Quality C'ontrol must perform process monitoring for AWS D1.1 welding every six months for each welder to assure that welder qualifications do not lapse. This welder was found to be included in the H. P. Foley Active Welder's List and was performing work as a qualified welder as of March 31, 1983. '
H. P. Foley procedure QCP-6 states in paragraph 6.4 that, "A
- list of qualified welders and brazers shall be maintained by the Quality Control Department. The list shall be revised t whenever there is a change in status." In paragraph 5.1, the ' '
procedure states that, " Welder qualification shall be effective providing the welder has used the process qualified for within the .following time periods: 6 months for welders qualified under Appendix "B", "C", "E", and "G"; or 3 months for welders qualified under Appendix "I"." Appendix C of the procedure describes the steps necessary to qualify a welder to the AWS DI.1, Structural Welding Code, latest revision, for groove welds of unlimited thickness. Successful completion of this qualification test also qualifies the welder for welding fillet welds on material of unlimited thickness. i QCP-5 further states in paragraph 5.1.1 that, "The Quality Control Department shall monitor each welder for each process qualified within the time period above to ensure that the jg welder's qualifications do not lapse." This welder's (symbol "JX") qualifications had effectively lapsed on January 27,
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1983. The failure to assure that welder qualification is maintained in accordance with procedural and code requirements is considered an apparent item of noncompliance with 10 CFR 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings." (50-275/83-13-02) (50-323/83-10-02) f.
Concern: The concern was expressed that the final typed ,i -
' version of Nonconformance Report (NCR) No. 8802-819, dated March 4,1983, varied substantially from the original rough draft of the NCR. This NCR documents a situation where, on j Ma'rch 2, 1983, H. P. Foley Quality Control Inspectors, assigned .
'to attend weld rod ovens in'the Fuel Handling Building, left j
the site before assuring that all weld rod was returned. On l this d.sy (March 2, 1983), the site was evacuated due to inclement weather and det'eriorating road conditions.
l NRC Findings: This concern was not substantiated.
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To address this concern,'the inspectors examined the final typed copy and earlier revisions of Nonconformance Report No.
i 8802-819. This examination did not identify any substantial
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change in the sentence structure or wording which could !
reasonably be interpreted as changing the intent, meaning or i
description of the nonconforming condition or of the recommended disposition. During this examination of the i
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nonconformance report and related data, the inspector noted that Inspection Report (IR) No. 8802-1344, written by a H. P.
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personnel, the NRC did perform a nationwide survey on this subject in June 1981'. The survey results were inconclusive. '
The ratio of inspector to craft varied anywhere from 1:1.7 l (WNP-2) to 1:26 (Palo Verde). In addition to the ~ contractor QA/QC organizations, the licensee maintains their own QA/QC .
- organization which provides for surveillance and audit of
- contractor activities. Furthermore, the licensee maintains a !
l- staff of personnel, assigned to each .of the Resident .
Electrical, Hechanical, Civil and Startup Engineers, who also provide for inspection and overview of the work performed by i
site contractors. These personnel further increase the ,
inspector /cr~ aft ratio.
The inspector considers that a substantial conclusion i
regarding the -adequacy of the inspector-to-craft ratio at Diablo Canyon during'this period cannot be establish-d with certainty.
No items,of noncompliance or deviations were identified.
- 6. Additional NRC Inspections l
During the course of interviewing individuals referenced in the testimony of the former Quality Control Manager and the Assistant Quality Control Manager, the NRC inspectors became concerned that methods used by the H. P. Foley Company for recertifying welder or
, welding operators might not meet the' intent of the ASME Code. This
. report identifies a similar problem wherein a welder was not recertified within the time limits specified by the AWS Code, as well as, contractor procedural requirements. This item is the subject of NRC enforcement action and is addressed in paragraph Se of this. report. This new NRC concern deals with the methods employed by H. P. Foley to recertify welders or welding operators.
The 1980 Edition of ASME Boiler and Pressure Vessel Code,Section IX, " Welding and. Brazing", Subarticle QW-322, " Renewal of Qualifications", states thap, " Renewal of qualification of a performance qualification is required: (a) when a welder or welding operator has not used the specific process, i.e. , metal-are, gas, submerged arc, etc., for a period of three months or more; except when employed on some other welding process, the period may be extended to six months; or (b) when there is a specific reason to question his' ability to make welds that meet the specification.
Renewal of qualification for *a specific welding process under (a) above may be made in only a single test joint (plate or pipe) on any thickness, position, o' r material to re-establish the welder's or welding operator's qualification for any thickness, position, or '
material'for which he was prevously qualified."
A review of forty H. P. Foley welder certifications determined that all welders were certified or recertified in accordance with H. P.
Foley's Quality Control Procedure, QCP-5 " Welder and Brazer Qualifications and.the Qualification of Welding and Brazing Procedures." However, the inspector noted that one welder, (symbol
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k S-4, recertified on February 19, 1983, to'an ASME Welding Procedure
- Specification'(WPS) No. M-03, a Gas Tungsten Arc Welding (GTAW) process), apparently was recertified by having the welder strike an ,
are with the nonconsumable tungsten electrode long enough for the l H. P. Foley Quality Control Inspector to take amperage and voltage I readings and record these readings on an In-Process Welding I Inspection Report. The report also indicates that no weld rod was
- issued during this time. The signature of the Quality Control Inspector on the In-Process Welding Inspection Report apparently !
accepts the recertification of the welder to the particular welding process. This particular welder was found to be on the H. P. Foley' Active Welders List, dated April 27, 1983. The NRC inspectors are ;
aware that this particular individual did not perform welding af ter j this certification. A review of employer payroll and weld rod withdrawal records indicated that this welder had been promoted to Foreman on January 18, 1983 and had not performed welding since that date. However, it is of concern that he had been placed on the-Active Velder'.s List and was considered ready and able to perform welding based on the re-certification of February 19, 1983. j For those welders that were re-certified and had not used a welding process for 3 months or more, the inspectors observed that the In-Process Welding Inspection Report fails to indicate whether the welders were recertified b! making a test joint (on a plate or pipe) i' or by in process welding in accordance with the Code. Thus, the inspector is concerned that the discrepant welder requalification process described above, may have been used to recertify welders currently appearing on the Active Welders List.
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It appears that measures were not established to assure that recertification of welders was accomplished in accordance with the l Code and the requirements of 10 CFR 50, Appendix B, Criteria IX, l " Control of Special Processes". This is an apparent item of noncompliance (50-275/83-13-04 and 50-323/F3-10-04) . -
- 7. Unresolved Items Unresolved it ems are matters about which more information is required in order to ascertain whether they are acceptable items, or items of noncompliance, or deviations. An unresolved item was identifled during this inspec, tion and is discussed in paragraph Sg
- of this report.
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