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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested 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 ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request 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 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses 1999-09-07
[Table view] Category:NRC TO OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT
MONTHYEARML20247E1141989-03-24024 March 1989 Requests FEMA Provide Evaluation of Upcoming 1989 Full Participation Exercise in Support of Licensing Schedule for Plant & Confirmation That Any Revs to State & Local Plans Since 1984 Have Not Degraded Effectiveness of Plans ML20246P4001989-03-23023 March 1989 Advises That Financial Assurances for Protection of Common Defense & Security Provided by Alchemie Accepted.Notifies That Any Activities by Alchemie Involving Access to Classified Machines & Info Must Be Under DOE Security ML20153G7431988-04-29029 April 1988 Advises That Second Graded Plant Exercise Will Be Conducted on 880607-09.State & Local Officials Refuse to Participate in Emergency Response Planning.Nrc Requests Space to Operate Federal Control Cell to Simulate State & Local Officials ML20151N2251988-04-26026 April 1988 Discusses Draft Control Plan & Request Review of Plan.If Agreement Reached,Plan Will Then Be Modified to Cover Seabrook Situation.Draft Control Plan Encl ML20211D9811986-10-14014 October 1986 Requests Fr Publication of Encl 861014 Notice of Environ Assessment & Finding of No Significant Impact,Approving Exemptions from Apps a & J & GDC 13 & 17.Publication Requested as Soon as Possible So Licenses Can Be Issued ML20214M0371986-08-22022 August 1986 Requests That Liquid Samples Spiked w/Sr-89,Sr-90,H-3 & Fe-55 Be Sent to Listed Region II Licensees,Except Farley, Per NRC Confirmatory Measurements Program.Samples Should Be Sent within Approx 2 Wks of Ltr Receipt ML20195E9161986-06-0404 June 1986 Forwards DM Stahl,Counsel for Commonwealth Edison Co,860527 Ltr Addressing Allegations of Illinois Municipal Electric Agency Re Need for OL Antitrust Review.Related Correspondence ML20211C6531986-06-0404 June 1986 Further Response to 850121 FOIA Request for Records Re Comanche Peak Task Force Established in Mar 1984.App O Documents 1-94 Available in Pdr.Portions of Documents 2-60, 63-77 & 88-94 Withheld (Ref FOIA Exemption 5) ML20198G7221985-12-18018 December 1985 Forwards Util Request for Exemption Re Plume Exposure Pathway Emergency Planning Zone.Nrc Reviewing Request. W/O Encl ML20235A7441985-12-17017 December 1985 Forwards Rept TEI-837, Geologic & Seismic Investigations of Proposed Nuclear Power Plant Site on Bodega Head,Sonoma County,Ca. W/O Rept ML20214F5951985-09-19019 September 1985 Forwards Std Order for DOE Work, Review of PRA for Seabrook Nuclear Power Plant, Authorizing Extension of Period of Performance from 850930 to 860930 Due to NRC Request to Meet W/Applicant Prior to Issuance of Final Rept ML20214F6031985-08-30030 August 1985 Forwards Std Order for DOE Work for FIN A-3778, Review of PRA for Seabrook Nuclear Power Plant, Authorizing Funds for Encl Statement of Work Mod ML20133N1721985-08-0707 August 1985 Requests Info Re Federal Response Ctr Locations for Incorporation Into Region I Incident Response Plan.Fema Region I Will Be Informed by Phone Upon Activation of Incident Response Ctr ML20133M9161985-08-0707 August 1985 Requests Federal Emergency Response Ctr Locations Proposed by FEMA Region II for Nuclear Power Stations on Encl List. Initial Contact Message That Will Be Used to Notify Region Upon Activation of Incident Response Ctr Encl ML20133B9771985-08-0101 August 1985 Ack Receipt of 850709 Request for Assistance in Obtaining Space & Equipment for FEMA Emergency Response Team Members at Plant Site.Nrc Will Meet W/Plant Representatives in Sept to Discuss site-specific Provisions & FEMA Request ML20138C1471984-09-13013 September 1984 Forwards,For Concurrence,Std Order for DOE Work, Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819.INEL Proposal Dtd Sept 1984 Acceptable.Lp Leach 850905 & 20 Ltrs to DOE Encl ML20138C1171984-08-24024 August 1984 Forwards,For Concurrence,Std Order for DOE Work,Changing Statement of Work for Evaluation of Selected NRC Open Items Before Plant Fuel Load, (FIN A-6819,Project 2) ML20138C1701984-07-31031 July 1984 Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl IA-84-751, Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl1984-07-31031 July 1984 Approves DG Bowers & H Margulies as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per Inel 840727 Request.Related Documentation Encl ML20138C0191984-07-18018 July 1984 Approves CM Rice & W Stratton as Subcontractors to Assist Inel in Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2,per LP Leach 840717 Request ML20138C0051984-07-0202 July 1984 Forwards Std Order for DOE Work,Supporting Evaluation of Selected NRC Open Items Before Plant Fuel Load, FIN A-6819,Project 2.Proposal Requested within 14 Days ML20127M9671983-10-20020 October 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Providing Addl Funding to Complete Work in Oct 1983 ML20128M7391983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20127M7991983-09-0202 September 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Operating Reactor Reviews for Indian Point & Zion, Providing Funds for Work During Oct 1983 ML20127A8241983-08-0404 August 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core- Melt Accidents;Operating Reactor Reviews for Indian Point & Zion ML20127A4471983-01-24024 January 1983 Forwards Std Order for DOE Work: Safety Evaluation of Core Melt Accidents:Indian Point-OR & Zion-OR, Providing Addl Funding for FY83 ML20127M2961982-12-30030 December 1982 Forwards Std Order for DOE Work: Safety Evaluation of Core-Melt Accidents:Indian Point Operating Reactor & Zion Operating Reactor, Accepting BNL 821203 Proposal & Providing Funds to Begin Work ML20148D9711978-10-19019 October 1978 Responds to Re Coordinating NRC & EPA for Review of Discharge Permit Appl,Amend to Constr Permit & Issuance of Operating Lic ML20126D8711973-03-12012 March 1973 Requests Assistance in Site Geologic Evaluation of Vogtle & Catawba Sites.Schedule for Input Dates Listed.Requests AEC & Schedule Dates Be Disregarded ML20235B6721972-11-30030 November 1972 Responds to to Chairman Schlesinger Re Plants. Applicants Advised That AEC Will Not Be in Position to Establish Final Position from Environ or Safety Standpoint Until Water Availability Question Further Clarified ML20235E1361972-08-21021 August 1972 Informs That on 720815,Licenses DPR-29 & DPR-30 Further Amended to Authorize Continuous Operation at 90% Rated Power w/diffuser-pipe Sys in Operation & Extending License Expiration Date to 731030 ML20235D4101972-02-14014 February 1972 Forwards PA Morris 720126 Response to Util Request for Authorization to Operate Plant Up to 50% Aggregate Station Power & Discussion & Conclusions Supporting Issuance of License to Util Authorizing 20% Operation of Plant ML20235B9341970-09-30030 September 1970 Forwards ACRS 700923 Repts on Listed Plants.W/O Repts for Indian Point Unit 2 & Midland Units 1 & 2 ML20235B5091969-12-15015 December 1969 Forwards Util Advising That Plans for Facility Deferred Until Future Date,For Info.Proposed Plant Would Have Been Located at Seabrook,Nh ML20235C7451968-07-16016 July 1968 Forwards 680618 Amend 1 to Util Application for License,Per 610801 Understandings ML20235C6901968-07-0202 July 1968 Forwards Notice of Receipt of Application for CP & Facility License & Vols I,Ii,Iii & IV of Psar,Per 610801 Understanding ML20235C6971968-07-0202 July 1968 Forwards Vols I,Ii,Iii & IV of PSAR as Part of Util Application for Licenses to Const & Operate Facility,Per Understandings in Udall ML20235D3111968-07-0202 July 1968 Requests Comments on Info Presented in Vols I,Ii,Iii & IV of Facility PSAR for Proposed Nuclear Power Station,Per Arrangements for Assistance in Evaluating Water Surge & Wave Runup Aspects ML20235D1471968-07-0202 July 1968 Requests Review of Util Application for Licenses to Const & Operate Nuclear Power Reactor Re Meteorological Aspects of Proposed Reactor Location.W/O Stated Encls ML20235D1891968-07-0202 July 1968 Forwards Vols I,Ii,Iii & IV of Facility Psar,Per Understandings Reflected in Udall to Seaborg. Results of Review Re Radiological Effects on Fish & Shellfish Requested ML20151X3221967-09-19019 September 1967 Informs of Forwarding Agency Rept Containing Comments & Recommendations on Both Radiological & non-radiological Effects of Proposed Operation of Nuclear Power Reactor at Diablo Canyon Site ML20151W8341967-02-0606 February 1967 Forwards Vols I & II of PSAR Filed Bu PG&E for Proposed Const & Operation of PWR at Util Site & Requests Rept Re Features of Proposed Reactor Operation Likely to Cause Radiological Effects on Fish & Shellfish by 670415.W/o Encl ML20151W9451967-02-0606 February 1967 Forwards Vols I & II of PSAR Filed by PG&E for Proposed Const & Operation of PWR at Diablo Canyon Site & Requests Rept on Meteorological Aspects of Proposed Reactor Location Which Might Have Bearing on Agency Safety Review.W/O Encl ML20235C8651966-11-10010 November 1966 Forwards GE & Attached Figure 3-1 Inadvertently Omitted from Amend 3 to Util Application for Const of Plants,Per 610801 Understanding Between AEC & Hew.W/O Encls ML20234F3621965-02-0404 February 1965 Expresses Appreciation for Cooperation & Caliber of Prof Assistance Received on Bodega Case ML20234F3891965-02-0404 February 1965 Expresses Appreciation for Cooperation & High Caliber of Prof Assistance Received on Bodega Head,Ca Case ML20234E7431964-12-0404 December 1964 Forwards Notice of Withdrawal of Application for Utilization Facility License for Publication in Fr ML20234E5131964-12-0404 December 1964 Forwards Util 641104 Request for Permission to Withdraw Application for License to Construct & Operate Nuclear Reactor at Bodega Bay,Ca & Notice of Withdrawal of Application.W/O Encls ML20235C7931964-11-0202 November 1964 Forwards ACRS 641020 Rept on Bodega Bay.Related News Clippings Encl.W/O Rept ML20235C7771964-11-0202 November 1964 Forwards ACRS 641020 Rept on Bodega Bay.W/O Encl 1989-03-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER 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 ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy 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 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H7501999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209G7421999-07-0808 July 1999 Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20 ML20196L0121999-07-0808 July 1999 Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i) ML20196K6771999-07-0202 July 1999 Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20196J0401999-06-29029 June 1999 Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan ML20196J4881999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid as Version 2 ML20196E6641999-06-22022 June 1999 Forwards Insp Repts 50-445/99-11 & 50-446/99-11 on 990418- 0529.No Violations Noted.Licensee Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance & Acceptable Radiological Control ML20207H3801999-06-0909 June 1999 Forwards Insp Repts 50-445/99-08 & 50-446/99-08 on 990503-11.Violations Identified & Being Treated as Noncited Violations ML20195G3771999-06-0909 June 1999 Ack Receipt of Ltr & Encl Objectives for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721.Based on Review,Nrc Determined That Exercise Objectives,Appropriate to Meet Plan Requirements ML20207G3291999-06-0707 June 1999 Ack Receipt of Which Transmitted Rev 27 to Comanche Peak Steam Electric Station EP Under Provisions of 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of EP No NRC Approval Required ML20207E9291999-06-0202 June 1999 Discusses 990526 Request That USNRC Exercise Discretion Not to Enforce Compliance with TS 4.8.2.1e Re Performance of Battery Performance Discharge Test,In Lieu of Battery Svc Test.Concludes Action Satisfactory & Discretion Exercised ML20207D7111999-05-28028 May 1999 Advises That Info Contained in Licensee 990514 Submittal Re License Amend Request 98-01-0 Will Be Withheld from Public Disclosure,Per 10CFR2.790. 10CFR2.790 ML20207D7011999-05-27027 May 1999 Advises That Info Contained in TU Electric 990514 Submittal (TXX-99115) Re License Amend Request 98-010 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 990511 Application & Affidavit ML20207B7241999-05-25025 May 1999 Advises That Info Contained in Application & Affidavit 990507 (CAW-99-1333),submitting WCAP-15004,dtd Dec 1997,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206Q0031999-05-14014 May 1999 Forwards Safety Evaluation Accepting Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Steam Electric Station,Unit 1 ML20206N7061999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206P5961999-05-12012 May 1999 Forwards Insp Repts 50-445/99-09 & 50-446/99-09 on 990419- 23.No Violations Noted.Nrc Determined That Releases of Radioactive Waste Effluents Controlled,Monitored & Quantified Well ML20206S5841999-05-11011 May 1999 Forwards Insp Repts 50-445/99-07 & 50-446/99-07 on 990307-0417.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint & Acceptable Radiological Controls ML20206K0311999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info,Without Encl ML20206H1701999-05-0606 May 1999 Forwards Copy of Exemption & Safety Evaluation Supporting Requirement in App K to 10CFR50.Proposal Will Use New Feedwater Flow Measurement Sys to Allow More Accurate Measurement to Thermal Power ML20206K3931999-05-0505 May 1999 Ltr Contract,Task Order 41, Comanche Peak Safety System Engineering Insp, Under Contract NRC-03-98-021 ML20206G1221999-05-0303 May 1999 Discusses 981215 Request That Document, Responses & Further Clarifications to NRC Questions from 980929 Meeting, Be Withheld from Public Disclosure.Determined Information to Be Proprietary & Will Be Withheld from Public Disclosure ML20206F5711999-04-30030 April 1999 Forwards Insp Repts 50-445/99-06 & 50-446/99-06 on 990329-0402.No Violations Noted.Insp Re Focus on Radiation Protection Program Activities During Unit 2 Refueling Outage ML20206E5211999-04-27027 April 1999 Discusses GL 96-01 Issued on 960110 & TU Responses, ,970102 & 980502 for Cpses,Units 1 & 2.Determined That Submittals Provided Both Info Requested & Responses Required by GL 96-01 ML20206B3831999-04-23023 April 1999 Forwards FEMA Final Rept for 990311,Comanche Peak Steam Electric Station Medical Drill.No Deficiencies or Areas Requiring Corrective Actions Identified ML20206B5321999-04-22022 April 1999 Ack Receipt of Ltrs Dtd 970407,09 & 0204,which Transmitted Revs 6 & 7 to Safeguards Continency Plan,Rev 10 to Security Training & Qualification Plan & Rev 29 to Physical Security Plan Submitted Under Provisions of 10CFR50.54(p) ML20206A2301999-04-14014 April 1999 Refers to Public Meeting Conducted on 990329 in Glen Rose, Tx Re Results of Plant Performance Review Completed on 990211 & Transmitted to Licensee on 990319.List of Attendees Encl ML20205L8711999-04-0707 April 1999 Forwards Insp Repts 50-445/99-03 & 50-446/99-03 on 990124-0306.No Violations Were Identified.Review of Operability Evaluation Re MOVs Disclosed That Licensee Failed to Include Info About Degraded ECCS Performance ML20205L1051999-04-0606 April 1999 Informs of Completion of Review of Tuec 980312 Submittal Re GL 97-05, SG Tube Insp Techniques. No Concerns Identified with SG Insp Techniques Employed at Cpses,Units 1 & 2,that Would Indicate Noncompliance with Current Licensing Basis ML20205F9141999-04-0101 April 1999 Informs That as of 990329 Dh Jaffe Has Been Assigned as Senior Project Manager for Plant IR 05000446/19920491999-03-24024 March 1999 Discusses Concern That Postulated Fire in CR Could Create Single Hot Short in Control Circuitry of MOVs Resulting in Spurious Operation.Required Hardware Mods Implemented to Control Circuits of Affected Mov,Per Insp Rept 50-446/92-49 ML20204F3311999-03-23023 March 1999 Forwards Discussion Items for 990323 Telcon 1999-09-07
[Table view] |
Text
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<4 y '~ y#c, UNITkD STATES
-[;- ~h p
NUCLEAR REGULATORY COMMISSION WASMNGTON, D. C. 20555 g ~
e--. C July 2,1984 Mr. Troy E. Wade, III, Manager Idaho Operations Office U.S. Department of Energy 550 2nd Street -
Idaho Falls, Idaho 83401 .
Dear Mr. Wade:
SUBJECT:
INEL TECHNICAL ASSISTANCE TO THE DIVISION OF LICENSING, NRR,NRC:
" EVALUATION OF SELECTED NRC OPEN ITEMS BEFORE PLANT FUEL LOAD" FIN A-6819, PROJECT 2
- The enclosed NRC Form 173, Standard Order for DOE Work, for $100K is submitted in accordance with Section III.B.2 of the DOE /NRC Memorandum of Understanding of February 24, 1978.
This work is urgently required to support the subject work and the Standard Order for DOE Work (50EW) is forwarded without prior proposal. The work authorization provides for proposal The enclosed Statement of Work (S0W) details preparation the requiredaswork partand of the workbescope.
should used as the basis for preparing a proposal. NRC Form 189 contains the minimum information needed and will be used for the proposal. Standard tems and conditions for NRC work, as approved by Headquarters, DOE, apply to this
~
effort. A copy of these tems and conditions has been furnished your office separately. We have discussed the enclosed 50W with Mr. B. Barnes of INEL and preliminary agreed in the schedule and estimated leve of effort. The proposal should be submitted within 14 days in six copies to:
U.S. Nuclear Regulatory Comission Office of Nuclear Reactor Regulation Attn: Mark Williams, Chief, TAPMG -
Washington, DC 20555 Please indicate DOE acceptance by signing and returning the enclosed NRC Form.173 to the NRC Office of Resource Management, Division of Accounting and Finance, with a copy to this office.
Work under this program is not anticipated to be classified, but it may I concern proprietary infomation that is provided in licensee proprietary reports and should be handled .in accordance with the Rule of Practice, 10 CFR 2.790.
l . .
8510220154 851016 PDR FOIA n CARDE84-751 PDR fj h
i...,
July 2,1984 Mr. Troy E. Wade -
2- .
\
If you have any questions, please contact Mark Williams (FTS 492-8461).
Thank you for your assistance.
Sincerely, Da r re.11. .G. .E i s e nhu t , Di re c to r . .
Division of Licensing
Enclosure:
- 1. NRC Fom 173 2.. Stat'ement of Work cc w/enil:
See next page.
em e
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July 2,1984 Troy E. Wade, Manager -
3- -
U.S. Department of Energy Idaho Operations Office 550 2nd Street Idaho Falls, Idaho 83401 cc: Mr. Robert W. Barber Office of Nuclear Safety - EP-34 U.S. Department of Energy Washington, DC 20545 Mr. Darrell Lewis U.S. Departrent of Energy-Idaho Operations Office 550 2nd Street Idaho Falls, Idaho 83401 Mr. R. E. Tiller U.S. Department of Ener gy Idaho Operations Office 550 2nd Street Idaho Falls, Idaho 83401 Mr. P. Litteneker U.S. Department.of Energy Idaho Operations Office '
E50 2nd Street
. Idaho Falls, Idaho 83401 Mr. E. W. Roberts Idaho National Engineering Lab EG&G Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. C. Obenchain -
Idaho National Engineering Lab EG&G Post Office Box 1625 Idaho Falls, Idaho 82415 Mr. B. Barnes Idaho. National Engineering Lab
_ EG&G Post Office Box 1625 Idaho Falls, Idaho 82415 I e e
I
NRC roam 173 v.s. nucle AR RE GULATORY COuutsslON ORDE R Nuu.E Q
'5#'
.. 20 'la ^99 DATE STANDARD ORDER FOR. DOE WORK July 2,1984 issut D av: (NRC Of f.ce) ACCOUNTING CITATION.
ISSUE D TO: IDOE Of fical Office Of Nuclear Reactor' ^*'a o'a '^T 'o" S* *o' Idaho Operations Office Regulation 31X0200.204
- um nu-na rERFORMiNG ORG ANiZanON AND LOCATION 20-19-40-41-1
_ _ . .. Piu ~vo.c a Idaho National Engineering Laboratory A-6819-4 Idaho Falls, Idaho _ . . _ . wor K rE Rico . THis ORoER
""" FlxED 0 ESTIMATED O Evaluation of Selected NRC Open Items Before ,,oo yo:
Plant Fuel Load 04/02/84 11/30/84 OSLtGATION AVAILABILITY PnOVIDED BY:
A. THIS ORDER S
100,000
- 8. TOT AL OF ORDERS PL ACE O PRsOR TO THis D ATE w TM THE Pf RFORMING ORG ANIZ ATION $
UNDE R THE SAME "APPROPRI ATION SYMBOL" AND THE FIRST FOUR DIGITS OF THE 5_1?n nnn n A ~uMeeR cited AeOvE
~
C. TOTAL ORDERS TO DATE . (TOTAL A & Bi 55,420,000 D. AMOUNT INCLUDE D IN "C" APPLIC A8LE TO THE ** FIN NUMBE R" CITED IN THIS OR DE R. S432 000 FINANCI AL FLExl81LITY:
@ FUNDS WILL NOT BE REPROGR AMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON O8 LIGATIONS .
AUTHORIZED.
O FUNDS MAY BE REPROGA AMM"ED NOT TO EXCEED
- 10% CF FIN LEVEL UP TO $50K. LINE C CONSTITUTE.5 A LIMITATtON ON CBLICATIONS AUTHORIZEO.
STANDARD TERMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THl$ ORDER UNLESS OTHERWISE NOTED.
ATT ACHM E NTS:
THE FOLLOwiNG ATTACMMENTS ARE HERE8Y SECURITY:
MADE A PART OF THIS ORDER: @ WORK ON THIS OROER 15 NOT CLAS$1FIED.
G STATEME NT O F WOR K O WORK ON TMiS OsDER inv0tvES CLASSIFIED INF ORM ATION NftC FORM 18715 ATTACHED.
, O ADDITION AL TERMS AND CONDITIONS O OTHER REMARKS (Reference the proposst b,f number and date. and indscote of the ettsched statement of work modofres the ODE proposen-i
. his T ' order provides incremental funds to initiatework that is urgently needed in accordance with the attached Statement of Work;*(50W) and requests that INEL submit a proposal based on the 50W within-14. days to M. Williams, NRR/DL with a copy provided to L. Solander, NRR/PPAS. This work authorization provides proposal preparation as part of the work scope.
After acceptance, please send to the NRC Office of Resource Management, ATTN: D. Dandois, and provide a copy to tne Office of Nuclear Reactor Regulation, ATTN: K. McGrath.
M (ts3UINQ AUTHORtTY ACCEPTING ORGANIZATION
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, arrell G. Eisenhut -
3t ' t.i t i Director, Division of Licensinc l .aC FOav its es.isi I
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, DATE: July 2,1984 -
.s l
STATEMENT OF WORK
Title:
Evaluation of Selected NRC Open Items Before Fuel Load (Program I) !
B&R Number: 20-19-40-41-1 i FIN Number: A-6819 !
i
. Total Estimate Level of Effort:' 5.3 direct technical staff years !
Projected Completion Date: November 30, 1984 Add the following paragraphs to the NRC Statements of Work attached to NRC .
i Forms 173 dated March 30, May 3, and May 12, 1984, and INEL proposal dated April 1984 for FIN A-6819:
" Project 2: Resolution of Comanche Peak Allegations i
NRC Project Manager: J. Donohew (FTS 492-7230) i NRC Lead Engineer: T. A. Ippolito or designated Group Leaoer l Cognizant Mana.ger: Mark Williams
~ Projected Completion Date: November 30, 1984 Estimated Level of Effort: 2.93taff years in FY84 1 0.1 staff years in FY85 A. BACKGROUND Comanche Peak Sterm Electric Station is. in the final stage,s of ihe operating license review process. The Construction Permits for Unit 1 and 2 were issued ;
on December 19, 1974. Texas Utilities docketed their application for operat'ing !
licenses on April 25, 1978. The Final Environmental Statement was issued. !
September 24, 1981. The Safety Evaluation Report (SER) was issued on July 14, 1981. Because of the large number of outstanding issues identified in the SER,
. t the staff recomended delaying the ACRS review. SER Supplement No. I was issued on October 16, 1981, and the ACRS meeting was held on November 13, 1981. The ACRS, by letter dated November 17, 1981, supported issuance of an operating !
license. The latest SER supplement was issued on November 23, 1983. j Comanche Peak has been in a heavily contested hearing for over two years.
All but one contention have been dismissed. The remaining contention questions the ability of the applicant's Quality Assurance / Quality Control Program to -
4 prevent deficiencies in the design and construction of the plant. The Licensing Board has admitted many allegations of design and construction >
deficiencies into the hearing as reisvant to this contention. For details see enclosed " Comanche Peak Plan for the completion of Outstanding Regulatory [
- Actions." '
The applicants are currently projecting a fuel load date for Unit I to be in '
late September 1984. The number of hearing issues and the timing of evaluating these issues may impact this date. . .
i
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~.
B. OBJECTIVE The objective of this effort is to assist the NRC in determining whether the alleged improper practices during the construction at Comanche Peak are valid and whether any dcpartures from proper practice are significant to the safety of the plant and have generic implications concerning other quality control ~
practices or other safety systems at the plant and in determining whether there is proper implementation of the applicant's and. vendor's quality assurance programs at the plant site. ___. _ _ _ _
C. WORK REOUIREMENTS
- 1. The contractor shall have a team composed of a team leader and team members and decide upon a plan .for performing the evaluation required in Task 3 below. The plan shall be presented to the NRC Le~ad Engineer at the site for his approval.
- 2. The contractor shall provide assistance to NRC Teams at the plant site identified by the NRC Lead Engineer. The INEL team will interface with the NRC teams through the INEL team leader.
- 3. By a review of the QA/0C documentation and associated information, and interviews with appropriate personnel, the contractor will:
5 ..
~
- a. review the implementation of the licensee's quality assurance program (including vendor programs) and provide a technical assessment regarding program implementation.
- b. based on their review of program implementation (a) and additional reviews regarding specific allegations, provide a technical assessment of allegations concerning improper p.ractices at the facility. Specifically, their assessment of the safety significance of the ,
reviewed allegations and the potential generic
. implications of the allegations.
Work assignments described above (a & b) will be made by the NRC Lead Engineer.
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~
i 4 The contractor's team leader s: tall report daily to the NRC Lead Engineer on the progrest and status of the program.
- 5. The contractor shall report his findings daily to the NRC Team Leaders identified by the FAC Lead Engineer.
- 6. The contractor shall present all his findings and conclusions for an assignment evaluating allegations in Task 3 above in a report to the NRC. Lead Engineer. A copy.of this report will be in the interim report and in the Technical Evaluation Report to the NRC Project Manager, ,
D. CRITERIA
- 1. The licensee's applicable quality control procedures at the plant site. ;
~
- 2. Appendix B to 10 CFR Part 50. Quality Assurance Criteria for Nuclear Plants and Fuel Reprocessing Plants.
- 3. Applicable industry standards.
4 Direction from the NRC Lead Engineer.
- 5. Attached Worksheet for review of allegations. .
E. MEETINGS AND TRAVEL .
- 1. There will be up to 84 d'irect technical staff weeks at the plant site at up to 6 days a week and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> a day expended by the contractor's team. This team will be up to a maximum of twelve people and will visit the site up to 7 different times during the period of performance.
- 2. A one-day, two-person visit to'NRC Offices at Bethesda, ' '
Maryland, is expected for presentations of findings and conclusions. .
l
- 3. Monthly, progress review meetings between the NRC Project Manager
'and the Contractor Program Manager will be conducted in Bethesda, Maryland, at INEL headquarters; at the plant site or by phone.
4 No other travel is allowed without prior approval by the NRC Project Manager.
- 5. Overtime snust be authorized by the NRC Project Manager. - ,
I e r
e
F. PLANTS AFFECTED AND SCHEDULE This assignment is concerned with the following plant:
Docket No.
"~
Comanche Peak 50-445
' ~
G. LEVEL OF EFFORT AND PERIOD OF PERFORMANCE The level of effort for this project is estimated to be 3.0 staff-person years over a 6-month period beginning July 9,1984.
H. REPGRTING RE0VIREMENTS
- 1. An interim report as required in paragraph C.6, will be provided on a date agreed upon by the NRC Lead Engineer and Project Manager but not later than September 30, 1984.
- 2. A final Technical Evaluation Report summarizing the work and the findings and conclusions'of the contractor will be.provided four weeks after the interim report.
- a. Technical.hvaluationLetterRecort The contractor shall provide the NRC Technical Assistance Program Manager with four copies of the final Technical Evaluation Letter Report (TER) which summarizes the results of the contractor's evaluation. The NRC Lead Engineer shall be sent one copy f the final TER. The
- letter will clearly identify the contractor, the FIN number and plant for which the TER was written.
An Interim Report will be provided to the NRC Lead Engineer shortly after the conclusion of the plant visit which briefly documents the results of the contractor's evaluation. The femat for this report will be approved by the NRC Lead Engineer.
NOTE: The interim report should be sent to the NRC Project fianager one week after the last vist to the plant site. The report should briefly summarize the conclusions of the contractor and include
, a copy of the contractor's reports-on his evalutions of the '
assigned allegations and his Feview of the applicant's implementation of his QA program.
~
. 5-The following information shall be included in the title page for the interim and final TER.
- a. Contractor's TER Identificatoin Number
- b. Program or Project Title
- c. Subjects -
- d. Author (s)
- e. . Responsible NRC Individual and Office or Division
- f. NRC FIN Number
- g. Document Date
- h. Plant Name and Docket Number
- 1. Contractor Personnel, other than the author (s), who have reviewed the TER.
In~ addition, the following notice shall be included on the inside front cover:
NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of
~ their employees, makes any warrant, expressed or. implied,
--( ' j for assumes any legal libability or responsibili.ty for any third party's use, or the results of such use, of any information, apparatus project or process disclosed in this report or represents that its use by such third party would not infringe privately owned rights.
Prior to completing and forwarding the final TER, the contractor shall provide a draft to the NRC Lead Engineer for his review and comments. The draft TER and the Interim Report shall be clearly marked showing that it is a draft report and, in addition to the above infonnation, shall include the following notice:
"This document was prepr. red primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be considered final."
S I e
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As a minimum, the TERs shall also have an Abstract,* a Table of Contents, and a Foreword. The Abstract will briefly discuss the subject and conclusion of the TER. The Foreword will-have the following paragraph:
FOREWORD This report is supplied as part of the (Title of Project) being conducted 16r The U. S. Nuclear -
. Regulatory Commission, Office of Nuclear Reactor
~
Regulation, Division of Licensing, by (contractor).
The U. S. Nuclear Regulatory Commission funded the work under authorization B&W (from NRC form 173)
FIN No. .
- b. Monthly Business Letter Report A monthly business letter report shall be submitted by the-15th of the month to the Director, Division of Licensing, with copies to the cognizant Manager, DL Project Manager, NRC Lead Engineer, NRC. Lead Project Manager (provided by
. s, the DL Project Manager) and Mr. Lars Solander, NRR. These
-:q reports will identify the title of the program, the FIN, the contractor program manager, the period of performance and the reporting period and shall contain three sections as follows:
Project Status Section This section will contain the following for each project: ,
- 1. A brief. description of the Task,
- 2. The progress during the previous month including- the major milestones reached, or if missed, an explanation provided, 3.- The problem or delays encountered or anticipated and actions that have been taken for their resolution,
- 4. The summary of the progress through the previous month, and
- 5. Plans for the next month.
v e e , --w..- .- , , -
FinancialwitnTRC accordance StatusManiial Section and Chapter Feeare y Section 1102 ~
Recover in I. .
PROPRIETARY INFORMATION the Government in connection with thiIf proprietary or co release such information s contract, to any the contractor person notagrees tos prov disafegu
.790 and agrees not to of NRC the work underOfficer.
Contracting this contract unless such release isrectly involve returned to the Comission.all copies of any such proprietary or c --
J, confidential data will beontract, NRC FURNISHED MATERIALS at the plant site.The NRC will provide the list of alleged i K. mproper practices to the contractor Ecuioment
- m. -
Any purchase of equipment required for th
\
Information to be provided approval: description in the letter e perfomance trequires of work under roval by the NRC Project Manager prior no this project schedule to receive eq,uipment,oand the NRCtotal Projeet Manager requesting costpurpose,
, serial number, man"facturer mod s
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WORKSHEET
- 1. Alleged " Improper" Qualit[ Control Pra,_ct.
ice: .
- 2. " Proper"- Approved Quality Control Practice:
R. -
- 3. A'c.tual Practice Followed:
. 4. . Departure, if any, from " Proper" Practice:
- 5. . Significance of Departure on Safe Plant Operation (e.g., systems /
instrumentation / equipment not functioning properly when . called on):
e t 9 4
~ ... . .
- r. .
s=
- 2-
- 6. Generic Implications of Departure on Other Practices or Other -
Equipment / Systems:
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.. l July 2,1984 Troy E. Wade, Manager U.S. Department of Energy Idaho Operations Office :
550 2nd Street i Idaho Falls, Idaho 83401 cc: Mr. Robert W. Barber Office of Nuclear Safety - EP-34
'0.S. Department of Energy Washington, DC 20545 ___ ,
Mr. Darrell Lewis -
U.S. Department of Energy Idaho Operations Office 550 2nd Street Idaho' Falls, Idaho 83401 Mr. R. E. Tiller U.S. Departmer.t of Energy Idaho Operations Office 550 2nd Street Idaho Falls, Idaho 83401 Mr. P. Litteneker U.S. Department.of Energy
- g. '
Idaho Operations Office 550 2nd Street Idaho Falls, Idaho 83401 Mr. E. W. Roberts Idaho National Engineering Lab EG&G Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. C. Obenchain -
Idaho National Engineering Lab EG&G Post Office Box 1625 Idaho Falls, Idaho 82415 Mr. B. Barnes Idaho National Engineering Lab .
EG&G Post Office Box 1625 Idaho Falls, Idaho 82415 kk '
DL:TAPMG D A NG DL.!5 1 -
- PP S D I
JDonohew W ams 'ip'/olito $ glia d ASolander . ,eanhut 6/d/84 6 /84 6/ /84 4 8 M W /84 6/984
,98 -
Dff' c hir.1 QK Mn emwmc m
i July 2,1984 l
. Troy E. Wade, Manager ' U.S. Department of Energy Idaho Operations' Office L 550 2nd Street "
Idaho Falls, Idaho 83401 cc: Mr. Robert W. Barber . .
Office of Nuclear-Safety - EP-34 ,
- U.S. Department of Energy !
Washington, DC' 20545 l Mr. Darrell Lewis -- !
U.S. Department of Energy :
Idaho Operations Office 550 2nd Street ;
Idaho Falls, Idaho 83401 Mr. R. E. Tiller U.S. Department of Energy !
Idaho Operations Office t 550 2nd Street (
Idaho Falls, Idaho 83401 Mr. P. Litteneker i
. U.S. Department of Energy .
- t Idaho Operations Office .
l 550 2nd Street ,
Idaho Falls, Idaho 83401 Mr. E. W. Roberts !
Idaho National Engineering Lab EG&G !
Post Office Box 1625- i Idaho Falls, Idaho 83415 Mr. C. Obenchain 1 Idaho National Engineering Lab !
EG&G Post Office Box 1625
' Idaho Falls, Idaho 82415- .
, Mr. B. Barnes Idaho National Engineering Lab !
EG8G Post Office Box 1625 Idaho Falls, Idaho 82415 !
- t. i . . ;
PMG DL:TAPMG AD:SA DL PPAS DL donohew MWilliams to FMiraglia JLeonard LSolander DEisenhut ,
6/1T/84 6/ /84 84 6/ /84 c/ /84 6/ /84 6/ /84 :
. -, , . _ , . . - . . . , ,