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Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20207L1901999-03-16016 March 1999 Informs That NRC Staff Set Up Single Electronic Mail Address to Receive All Communications (Including Service of Filings) Re CP&L Proceeding.All Electronic Communications Should Be Sent to Counsel for NRC Staff at New Electronic Address ML20207G5621999-01-12012 January 1999 Requests That Nc Denr & Div of Radiation Protection Use Whatever State Sources Necessary to Do Thorough Independent Technical,Regulatory,Safety,Risk & Engineering Review of Proposed Amend.With Certificate of Svc.Served on 990309 ML20198F1471997-08-0707 August 1997 Discusses Dam Safety Audit at Plant Auxiliary Reservoir Dam. Draft Ltr for Use in Transmitting FERC Rept to Licensee, Action List of NRC Requested Licensee Actions,Info Re Natl Inventory of Dams & Insp Rept,Dtd 970630,encl ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20128G5751996-10-0303 October 1996 Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations ML20134B7921996-06-24024 June 1996 Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model ML20134J1821990-07-12012 July 1990 Informs That Full Investigation Re Counterfeit Electrical Components Shipped to Shearon Harris Nuclear Plant Will Be Initiated ML20134H3841990-06-26026 June 1990 Requests That OI Investigate Circumstances Surrounding Possible Wrongdoing by Stokely Enterprises of Norfolk,Va & Spectronics of Mobile Re Misrepresented Potter & Brumfield Relays to Shearon Harris Nuclear Power Plant ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20195E6191988-06-13013 June 1988 Notifies of CRGR Meeting 138 on 880614 in Rockville,Md. Agenda Listed ML20154D8541987-12-30030 December 1987 Forwards Info on Auxiliary Feedwater Check Valves for Facilities Per IE Bulletin 85-001,in Response to 871229 Request ML20238A8041987-09-0303 September 1987 Notification of 870917 Meeting W/Util in Bethesda,Md to Discuss Tech Specs Improvement Program Per Generic Ltr 87-09 ML20238E0001987-09-0303 September 1987 Notification of Time Change for 870917 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 87-09 Re Tech Spec Improvement Program ML20195G3891987-08-21021 August 1987 Forwards Safety Evaluation Re Util 870526 Application for Amend to License NPF-63,increasing Max Allowed Enrichment of Reload Fuel to 4.2% Weight U-235.Changes Acceptable ML20195G2961987-07-14014 July 1987 Forwards Request for Addl Info Re Util 870526 Proposed Tech Spec Change Concerning Handling & Storage of Fuel W/Increased Enrichment to 4.2 Weight % U-235 NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR1987-05-13013 May 1987 Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR ML20209A9621987-04-28028 April 1987 Forwards Two Photographs of Separation Problem in Fuel Handling Bldg.Previous Pictures of licensee-identified Items Not Similar in Nature to Problem Identified by Ford ML20210L9561987-02-0505 February 1987 Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 ML20212G3021987-01-20020 January 1987 Forwards Attachments to Be Incorporated in Transcript Re Facility ML20207M0361987-01-0606 January 1987 Provides Current Status of Facility Proceeding,Including Admitted Contentions Raising Listed Issues.Aslb Issued Three Initial Decisions & Concluding or Final ASLB Decision Favorable to Applicants ML20207K8061987-01-0606 January 1987 Forwards Ltr Presented to Asselstine on 870105 to Be Served on Parties to Proceeding.Served on 870106 ML20215E9231986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20207E2271986-12-19019 December 1986 Notifies of Commissioner Asselstine 870105 Site Visit. Representatives of Interested Parties Invited to Attend. Served on 861219 IA-86-843, Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending1986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20212C6771986-12-15015 December 1986 Requests That Encl 861215 Minutes of 861210 Meeting W/ Coalition for Alternatives to Shearon Harris Be Placed in PDR ML20211L6521986-12-12012 December 1986 Advises That Time for Commission to Review ALAB-852 Expired. Commission Declined Review.Decision Became Final Agency Action on 861210.Served on 861212 ML20196B6441986-12-12012 December 1986 Forwards Ofc of Investigations Rept of Inquiry Re Alleged Falsification of Radiation Exposure Records & Alleged Discrimination (Q2-86-017).Partially Deleted Related Info Encl ML20215B1281986-12-10010 December 1986 Advises That Time for Commission to Review ALAB-843 Expired. Commission Declined Review.Decision Became Final Agency Action on 861031.Served on 861210 ML20206C0431986-12-0404 December 1986 Memo for Affirmation,Notifying That Commission Being Asked to Respond to Request from W Eddelman & Coalition for Alternatives to Facility for Hearing on Util Requested Exemption from Requirements for Emergency Exercise ML20215N6601986-11-0606 November 1986 Advises That Commissioner Bernthal Has Canceled Planned 861118 Visit to Facility.Served on 861106 ML20215N5681986-10-29029 October 1986 Forwards 860825-29 Rept Documenting IE Assessment of Three Technical Allegations Re Cable Tray Support Design at Facility.Allegation Re Load Carrying Adequacy of Connection Detail Used for Cable Tray Supports Included in Rept ML20215M4501986-10-28028 October 1986 Advises of Commissioner Bernthal 861118 Visit to Facility. All Representatives of Party to Proceeding Wishing to Attend Should Notify Author by C.O.B. on 861112.Served on 861029 ML20236F1641986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl IA-87-279, Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl1986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl ML20215J4321986-10-21021 October 1986 Forwards Trip Rept of 860825-29 Visit to Facility to Conduct Assessment of Technical Allegation Re Cable Tray Support Design.One Allegation Re Connection Detail Used on Cable Tray Substantiated ML20212G0401986-09-30030 September 1986 Forwards Background Info on Facility Per 860924 Request. Proposed Agenda for Chairman Lw Zech 860914-15 & Commissioner KM Carr 861050-06 Site Visits Encl ML20209A9981986-09-30030 September 1986 Notification of 861009 Enforcement Conference W/Util in Region II Ofc to Discuss Potential Deficiency in Const QA Program.Util Nonconformance Rept,List of Attendees & Util Presentation Viewgraphs Encl ML20214R5231986-09-24024 September 1986 Informs Parties That Commissioner KM Carr Will Tour Facility on 861006.Notification Requested by 861002 of Any Parties to Proceeding Wishing Single Representative Attendance. Served on 860924 IA-86-793, Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets1986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20237G4671986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20207S2361986-09-17017 September 1986 Advises That Commission Disapproved SECY-86-252, Commission Review of Shearon Harris Appeal Board Decision on Environ Issues ML20210B5561986-09-16016 September 1986 Forwards Ps Miriello Affidavit to Be Serve Upon Appropriate Parties & Boards in Pending Proceedings. Served on 860917 ML20214N4421986-09-15015 September 1986 Notifies That Time Provided by NRC Regulations within Which Commission May Act to Review ALAB-837 Expired.Served on 860915 ML20236F1421986-09-12012 September 1986 Forwards Lists of Items to Be Completed Prior to Fuel Loading,Per Insp Procedure 94300B.Licensee Projected Fuel Load Date Is Sept 1986 ML20209F9741986-09-11011 September 1986 Requests That 860911 Memo Re Emergency Planning Exemption Request Be Served on Parties to Proceeding.Served on 860911 ML20209G0191986-09-11011 September 1986 Discusses B Cummings Telcon Concerning Ltr Expressing Opposition to Util Request for Exemption to Emergency Drill Requirements 1999-07-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20207L1901999-03-16016 March 1999 Informs That NRC Staff Set Up Single Electronic Mail Address to Receive All Communications (Including Service of Filings) Re CP&L Proceeding.All Electronic Communications Should Be Sent to Counsel for NRC Staff at New Electronic Address ML20207G5621999-01-12012 January 1999 Requests That Nc Denr & Div of Radiation Protection Use Whatever State Sources Necessary to Do Thorough Independent Technical,Regulatory,Safety,Risk & Engineering Review of Proposed Amend.With Certificate of Svc.Served on 990309 ML20198F1471997-08-0707 August 1997 Discusses Dam Safety Audit at Plant Auxiliary Reservoir Dam. Draft Ltr for Use in Transmitting FERC Rept to Licensee, Action List of NRC Requested Licensee Actions,Info Re Natl Inventory of Dams & Insp Rept,Dtd 970630,encl ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20128G5751996-10-0303 October 1996 Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations ML20134B7921996-06-24024 June 1996 Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model ML20134J1821990-07-12012 July 1990 Informs That Full Investigation Re Counterfeit Electrical Components Shipped to Shearon Harris Nuclear Plant Will Be Initiated ML20134H3841990-06-26026 June 1990 Requests That OI Investigate Circumstances Surrounding Possible Wrongdoing by Stokely Enterprises of Norfolk,Va & Spectronics of Mobile Re Misrepresented Potter & Brumfield Relays to Shearon Harris Nuclear Power Plant ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20195E6191988-06-13013 June 1988 Notifies of CRGR Meeting 138 on 880614 in Rockville,Md. Agenda Listed ML20154D8541987-12-30030 December 1987 Forwards Info on Auxiliary Feedwater Check Valves for Facilities Per IE Bulletin 85-001,in Response to 871229 Request ML20238E0001987-09-0303 September 1987 Notification of Time Change for 870917 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 87-09 Re Tech Spec Improvement Program ML20238A8041987-09-0303 September 1987 Notification of 870917 Meeting W/Util in Bethesda,Md to Discuss Tech Specs Improvement Program Per Generic Ltr 87-09 ML20195G3891987-08-21021 August 1987 Forwards Safety Evaluation Re Util 870526 Application for Amend to License NPF-63,increasing Max Allowed Enrichment of Reload Fuel to 4.2% Weight U-235.Changes Acceptable ML20195G2961987-07-14014 July 1987 Forwards Request for Addl Info Re Util 870526 Proposed Tech Spec Change Concerning Handling & Storage of Fuel W/Increased Enrichment to 4.2 Weight % U-235 NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR1987-05-13013 May 1987 Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR ML20209A9621987-04-28028 April 1987 Forwards Two Photographs of Separation Problem in Fuel Handling Bldg.Previous Pictures of licensee-identified Items Not Similar in Nature to Problem Identified by Ford ML20210L9561987-02-0505 February 1987 Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 ML20212G3021987-01-20020 January 1987 Forwards Attachments to Be Incorporated in Transcript Re Facility ML20207Q2021987-01-16016 January 1987 Staff Requirements Memo Re 870108 Discussion/Possible Vote in Washington,Dc on Full Power OL for Plant.Commission Authorized Issuance of Full Power OL ML20207M0361987-01-0606 January 1987 Provides Current Status of Facility Proceeding,Including Admitted Contentions Raising Listed Issues.Aslb Issued Three Initial Decisions & Concluding or Final ASLB Decision Favorable to Applicants ML20207K8061987-01-0606 January 1987 Forwards Ltr Presented to Asselstine on 870105 to Be Served on Parties to Proceeding.Served on 870106 IA-86-843, Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending1986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20215E9231986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20207E2271986-12-19019 December 1986 Notifies of Commissioner Asselstine 870105 Site Visit. Representatives of Interested Parties Invited to Attend. Served on 861219 ML20212C6771986-12-15015 December 1986 Requests That Encl 861215 Minutes of 861210 Meeting W/ Coalition for Alternatives to Shearon Harris Be Placed in PDR ML20211L6521986-12-12012 December 1986 Advises That Time for Commission to Review ALAB-852 Expired. Commission Declined Review.Decision Became Final Agency Action on 861210.Served on 861212 ML20196B6441986-12-12012 December 1986 Forwards Ofc of Investigations Rept of Inquiry Re Alleged Falsification of Radiation Exposure Records & Alleged Discrimination (Q2-86-017).Partially Deleted Related Info Encl ML20215E0721986-12-11011 December 1986 Staff Requirements Memo Re 861204 Affirmation/Discussion & Vote in Washington,Dc Re W Eddleman & Coalition for Alternatives to Shearon Harris Request for Hearing on Util Request for Exemption from Full Scale Exericse ML20215B1281986-12-10010 December 1986 Advises That Time for Commission to Review ALAB-843 Expired. Commission Declined Review.Decision Became Final Agency Action on 861031.Served on 861210 ML20206C0741986-12-0505 December 1986 Staff Requirements Memo Re Affirmation/Discussion & Vote on Request for Hearing Re Facility Exemption Request.Order Finds No Matl Issues of Fact That Warrant Hearing ML20206C0431986-12-0404 December 1986 Memo for Affirmation,Notifying That Commission Being Asked to Respond to Request from W Eddelman & Coalition for Alternatives to Facility for Hearing on Util Requested Exemption from Requirements for Emergency Exercise ML20215N6601986-11-0606 November 1986 Advises That Commissioner Bernthal Has Canceled Planned 861118 Visit to Facility.Served on 861106 ML20215N5681986-10-29029 October 1986 Forwards 860825-29 Rept Documenting IE Assessment of Three Technical Allegations Re Cable Tray Support Design at Facility.Allegation Re Load Carrying Adequacy of Connection Detail Used for Cable Tray Supports Included in Rept ML20215M4501986-10-28028 October 1986 Advises of Commissioner Bernthal 861118 Visit to Facility. All Representatives of Party to Proceeding Wishing to Attend Should Notify Author by C.O.B. on 861112.Served on 861029 ML20236F1641986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl IA-87-279, Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl1986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl ML20215J4321986-10-21021 October 1986 Forwards Trip Rept of 860825-29 Visit to Facility to Conduct Assessment of Technical Allegation Re Cable Tray Support Design.One Allegation Re Connection Detail Used on Cable Tray Substantiated ML20212G0401986-09-30030 September 1986 Forwards Background Info on Facility Per 860924 Request. Proposed Agenda for Chairman Lw Zech 860914-15 & Commissioner KM Carr 861050-06 Site Visits Encl ML20209A9981986-09-30030 September 1986 Notification of 861009 Enforcement Conference W/Util in Region II Ofc to Discuss Potential Deficiency in Const QA Program.Util Nonconformance Rept,List of Attendees & Util Presentation Viewgraphs Encl ML20214R5231986-09-24024 September 1986 Informs Parties That Commissioner KM Carr Will Tour Facility on 861006.Notification Requested by 861002 of Any Parties to Proceeding Wishing Single Representative Attendance. Served on 860924 IA-86-793, Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets1986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20237G4671986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20203N3441986-09-19019 September 1986 Staff Requirements Memo on 860911 Affirmation/Discussion & Vote in Washington,Dc Re SECY-86-254,SECY-86-257 & SECY-86-258 ML20207S2361986-09-17017 September 1986 Advises That Commission Disapproved SECY-86-252, Commission Review of Shearon Harris Appeal Board Decision on Environ Issues ML20210B5561986-09-16016 September 1986 Forwards Ps Miriello Affidavit to Be Serve Upon Appropriate Parties & Boards in Pending Proceedings. Served on 860917 1999-07-27
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N May 8, 1986 MEMORANDUM FOR: Thomas M. Novak, Acting Director, Division of Pressurized Water Reactor Licensing-A, NRR FROM: Luis A. Reyes, Acting Director, Division of Reactor Projects I
SUBJECT:
CAROLINA' POWER AND LIGHT COMPANY - HARRIS UNIT 1 DOCKET NO. 50-400, STATUS OF FACILITY COMPLETION g_40C[(7, In accordance with Inspection Procedure Nc. 943008, the enclosures list the remaining open items that require resolution before a finding of readiness for i operation may be endorsed by Region II.
The licensee's projected fuel load date is July.25,1986. Region II considers this date to be realistic, assuming that no unforeseen delays occur in the i licensee's remaining construction and preoperational testing effort.
Original Signed by Virgil L. Brownlee /for I
Luis A. Reyes
{
Enclosures:
)
- 1. Items.to be Completed Prior to l Fuel Loading
- 2. Items to be Completed Prior to 4 Initial Criticality >
- 3. Items to be Completed Prior to Exceeding 5% Rated Power
- 4. Items to be Completed Prior to Full Power Operation
- 5. Pre ferotional Testing Status and Operational Preparedness
- 6. Construction Status
- 7. Status of Inspections Required by MC 2512, MC 2513, and MC 2514 cc w/cacis:
J. G. Partlow, Director, DQASIP E. L. Jordan, Director, DEPER G. T. Ankrum, Chief, Quality Assurance ,
Branch, DQASIP L. I. Cobb, Chief, Safeguards and Material Program Branch, DQASIP 4 R. F. Heishman, Chief, Reactor Construction Branch, DQASIP B. . C. Buckley, Licensing Project Manager, NRR bec w/encis: (See page 2) >
8708030214 870512 PDR FOIA ,
GRADER 87-279 N
PDR k
I
Thomas M. Novak 2 May 8, 1986 !
bec w/encls:
R. D. Walker .
G. R. Jenkins !
V. W. Panciera -
W. E. Cline A. R. Herdt T. E. Conlon C. M.-Hosey C. A. Julian .
C. M. Upright
, J. J. Blake ,
i D. R. McGuire 1
! P. E. Fredrickson F. Jape G. Maxwell S. Burris o
' 67Q ;
g
- D3/(, /86Pdredrickson:bhg DVerrelli' 0$/4/86 M Mellen yk son JP5tohr 06/G/86 f'$/l/86 '06/*)/86
- 4 May 8, 1986 ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING-(including licensee's projected completion date) 4 A. The licensee will complete, to the satisfaction of. the NRC, the following violations:
- 1. 83-29-01/RP2A Correct failure to control fastening material 2, 85-04-01/RP2A Correct inadequate inspection for electrical separation
- 3. 85-08-01/PSS Resolve inadequate design control for raceway separation l 4. 85-47-04/TPS Failure to provide Appropriate Acceptance criteria for TP 1-2005-P-01 B. The following unresolved items or deviations are required to be completed:
l 1. 82-24-01/MPS Resolve installation of nonsafety-related, nonseismic-supported, electrical conduit- in the vicinity of safety-related equipment or components
1 Enclosure 1 2 1
. . I
- 2. 84-44-04/MPS Resolve program for control of purchased materials j
- 3. 84-44-05/MPS Resolve program for inspection of activities 0 affecting quality 4-. 84-49-02/RP2A Resolve cable. tray overfill problem-
- 5. 85-08-02/PSS Staff approval of reduced separation between nonclassified conduit and open class IE raceway
- 6. 85-26-01/PSS Incorporation of instrument tubing separation criteria
)
- 7. 85-31-03/TPS Resolve Test Outline Reg. Guide 1.68
- 8. 85-33-01/RP2A Installation of Safety-related Equipment'
- 9. 85-37-02/RP2A Resolution of Concerns Associated with IE Bulletin 83-05 j
- 10. 85-37-03/RP2A Plant Organization Chart for Operations ;
- 11. 85-39-02/PSS Review causes of NCR 85-1665 for deportability
- 12. 86-02-02/TPS Test procedure 1-2000-P-01 and 1-8010-P-02 do not identify data recorder
a Enclosure 1 3 1
- 13. .86-04-01/TPS AFWS test objectives and acceptance criteria are not fully incorporated l
C. The following open and inspector followup items are required to be completed:
- 1. 83-27-01/MPS Unavailable steam generator. records
- 2. 84-24-05/RP2A Certifications for plant. general manager ;
i
- 3. 85-27-02/RP2A Plant nuclear safety committee procedure
- 4. 85-36-01/MPS Newly hired engineer training
- 5. 85-37-01/RP2A Difference between the as-built plant and the FSAR
- 6. 85-40-07/PSS Engineering Analysis Testing and Justification for Non-Standard Penetration Seal Configurations i l
- 7. 85-40-08/PSS Revisions Required to Fire Door Inspection Procedures to Meet NFPA Standards l
l l
- 8. 85-40-09/PSS Piping to Automatic Sprinkler System and Interior ,
1 '
l Fire Hose System for Diesel Generator Building. Fire Suppression Systems is Not Designed to Meet Single l
Failure Criteria as Required by FSAR
Enclosure 1 4
- 9. 85-40-11/PSS Reevaluation of Sprinkler System Obstructions 1
)
10, 85-40-12/PSS Two. Fire Pumps Are Not Provided for Supply to SSE i
Interior Fire Hose System 4
- 11. 85-40-13/PSS Reactor Coolant Pump Oil Collection System is Not
]
Designed to Maintain Structural or Pressure .
d Integrity Following a SSE and Was Not Constructed j i
Under A QA/QC Program ;
i
- 12. 85-40-14/PSS Procedure Required to Drain or Verify Reactor Coolant Pump 011 Collection System Drain Tanks Are Empty Prior to Startup
- 13. 85-45-01/FRP Contamination of Demin Water Systems (Circular 80-14) 14, 85-47-01/TPS Clarify Initial Condition 2 9 of T.P. 1-1100-P !
I
- 15. 85-50-01/ REC Water Chemistry Program
'16 . 85-52-02/RP2A Operational discrepancies of the component cooling ,
water system
- 17. 86-07-01/RP2A Independent Verification E_______________-_-________
. l Enclosure 1 5
- 18. 86-10-01/TPS Clarify Procedure AOP-004
- 19. 86-20-01/TPS Revise Initial Fuel Loading Procedure
- 20. 86-20-02/TPS Revise RCS Leakrate Procedure 1
- 21. 86-20-03/TPS Revise Initial Criticality Procedure !
l
- 22. 86-20-04/TPS Revise Boron Endpoint Procedure !
- 23. 86-16-01/RP2A Teflon Tape in the RHR System i
l l
l D. The licensee will complete, to the satisfaction of the NRC, the following 10 CFR 50.55(e) and 10 CFR 21 items:
- 1. CDR80-41/PSS Protection system following a secondary high energy line rupture (Steam Generator Ref Leg Heatup)
- 2. CDR83-130/PSS Potential deficiency with Westinghouse DS 416 breakers l
- 3. COR84-162/PSS Fire barriers-Tack welds
- 4. CDR85-179/TPS In-core flux mapping system-system interactions l 5. COR84-183/MPS Potential overpressurization of the component cooling water system
'4 Enclosure 1 6 l l
1 61 CDR84-188/MPS Air operated diaphragm valves do not. meet design value for r.atural frequency
- 7. CDR84-191/PSS 7.5 KVA inverters / insulation breakdown
- 8. CDR85-209/MPS 6.9 KV swit,chgear circuit breakers, secondary disconnect fingers 9 3
- 9. CDR85-213/PSS Undetected failures in ESF actuation system !
l l
- 10. CDR85-214/MPS Standby DG, control panel ventilation
- 11. CDR85-215/MPS Westinghouse safety grade core exit thermocouple
- 12. CDR85-219/MPS Emergency service water pumps - material failure l
.I
- 13. CDR85-220-PPS Emergency diesel generator - control panel wiring
- 14. CDR85-223/PPS Emergency diesel - intake and exhaust valves E. The licensee will complete, to the satisfaction of the NRC, the following IE Bulletins:
- 1. 78-BU-12/MPS A typical weld material in reactor pressure vessel welds
.o Enclosure 1 7 I
- 2. 79-BU-18/EPS Audibility problems encountered on evacuation of personnel from'high-noise areas
- 3. 80-BU-10/FRP Contamination of nonradioactive system and resulting potential for unmonitored, uncontrolled release of radioactivity to environment
- 4. 80-BU-11/TPS Masonry wall design i
- 5. 82-BU-02/MPS Degradation of threaded fasteners in the reactor coolant pressure boundary of PWR plants
- 6. 83-BU-05/MPS ASME Nuclear Code pumps and space parts manufac-tured by the Hayward Tyler Pump Company
- 7. 84-BU-03/TPS Reactor vessel inflatable seal F. The licensee will complete, to the satisfaction of the NRC, the following TMI Action Plan Requirements:
- 1. I.A.1 (85-16-01)/RP2A Shift supervisor administrative duties
- 2. I.C.6 (85-16-04)/RP2A Verify correct performance of operating activities
- 3. I.D.1 (85-16-06)/RP2A Control' room design review L______________-__-_-__
Enclosure 1 8
- 4. II.D.1 (85-16-11)/RP2A Performance testing of boiling water reactor and pressurized water reactor relief and safety valves
- 5. II.D.3 (85-16-12)/RP2A Relief and safety valve indication
.~
- 6. II . F.1 (85-16-17)/RP2A Subparts (4) and (5) containment pressure l
and water level monitors
- 7. II . F.1 (85-16-18)/ REC Subpart (6) containment hydrogen concentration monitor ;
- 8. II.F.2 (85-16-19)/RP2A Instrumentation for detection of l inadequate core cooling
- 9. II.K.1.5 (85-16-z2)/RP2A Review of ESF valves
- 10. II.K.1.10 (85-16-22)/RP2A Operability status
- 11. II.K.3.5 (85-16-24)/RP2A Automatic trip of reactor coolant pumps during LOCA
- 12. III.A.I.2 (85-16-25)/EPS Upgrade emergency support facilities
- 13. III.A.2 (85-16-26)/RP2A Improving licensee emergency preparedness long term
Enclosure 1 9
- 14. III.D.3.3(85-16-28)/FRP Improved inplant iodine instrumentation under accident conditions
- 15. I.D.2 (85-16-29)/RP2A Plant safety parameter display console
- 16. II.B.2 (85-16-32)/FRP Plant shielding to provide access to vital areas l
i
.f
May 8, 1986 ENCLOSURE __2 ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY The following open and inspector followup items should be closed:
85-09-82/EPS Demonstrating the capability to perform staff augmentation within applicable time frames
i
- j May 8, 1986 )
l ENCLOSURE 3 J l
l 1
I ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 5% RATED POWER l
A. The following unresolved items are required to be completed:
. 1 85-14-01/RP2A Resolve scheduling. and conduct of' battery.
equalizing charges 85-24-03/RP2A Overload trip set points for ITE type HE3-M040.-
molded case circuit breakers B. The following open and inspector followup items should be closed:
1 84-26-01/PSS Review of fire protection QA/QC program to address accessibility / operability and design requirements of NFPA fire codes ,
. . i 85-09-27/EPS Verify the completion of Turbine Building first aid I room and deployment of on-site ambulance kit 85-09-28/EPS Finishing of Turbine Building drum room and equipping of waste processing and ,TSC drum facilities
Enclosure 3 2 85-09-65/EPS Reviewing of applicant personnel accountability procedures 85-09-66/EPS Reviewing of Security program during emergencies 85-27-01/RP2A Sheathing bu,1ges in absorber cells 85-40-01/PSS Fire Protection Systems, Features and Administra-tive Procedures are Required to be Operational Prior to Fuel Load 85-40-02/PSS Revisions Required to Fire Protection / Prevention Procedures in Order to Meet NRC Guidelines 85-40-03/PSS Incomplete Operation Surveillance Test Procedures for Fire Protection Features 85-40-04/PSS Operation Surveillance Test Procedures are Wot Developed and Issued for Permanent Plant Fire Protection Features 85-40-05/PSS Additional. Personnel Required to be Provided with Fire Brigade Training Prior to Fuel Load 85-40-06/PSS Fire Brigade Equipment and Storage Lockers are Required to be Provided Prior to Fuel Load
4 Enclosure 3 3 85-40-10/PSS Verification that Pre-Action Fire Suppression Valve Installations Conform to the Manufacturer's Requirements 85-40-15/PSS Review of Completed Fire Detection System Inspections a,nd Pre-Operational Tests j
85-46-01/EPS Insuring that the Unusual Event matrix of PEP-101 I is sufficiently wide in scope to include any event causing rapid depressurization of the secondary side 85-46-02/EPS Verify TSC positive pressure specification i
.May 8, 1986 ENCLOSURE 4 l l
ITEMS TO BE COMPLETED PRIOR TO FULL POWER OPERATION The licensee will complete, to the satisfaction.of the NRC, the following TMI Action Plan requirements: ,-
~1 I.C.1'(85-16-02)/RP2A Guidance for'the evaluation and development l of procedures for transients and accidents I.C 7.1 (85-16-05)/RP2A NSSS vendor review of low power test procedure I.G.1 (85-16-07)/TPS Special low power' testing and training II.B.1 (85-16-08)/RP2A Reactor coolant system vents-II.B.3 (85-16-09)/ REC Post-accident sampling capability II.B.4 (85-16-10)/RP2A Training and mitigating core damage II.E.1.2 (85-16-13)/RP2A Auxiliary feedwater syst'em initiation and
't flow II.E.4.2 (85-16-14)/RP2A Containment isolation dependability ,
7 1
... l
.- k Enclosure'4 2 II.F.1 (85-16-15)/ REC Subparts (1) and (2) effluent radiological !
monitoring sampling and analysis i
II.F.1 (85-16-16)/FRP Subpart (3) containment high-range radiation monitor i
. b III.D.1.1 (85-16-27)/RP2A Integrity of systems outside containment
-likely to contain radioactive material I.C.7.2 (85-16-31)/RP2A NSSS vendor review of power ascension procedures l l-
I May 8, 1986 i
ENCLOSURE 5 I j
PREOPERATIONAL TESTING AND OPERATIONAL PREPAREDNESS As of April 22, 1986, the overall status of the test program is summarized below:
i
)
i Total Tests Completed In Progress Not Started l
Preops Required k for Fuel Load 166 78 19 69 .
?
l Preops Required After Fuel Load 52 0 0 52 i
i i
i l
May 8, 1986
'dNCLOSURE 6 CONSTRUCTION STATUS As of April 22, 1986, construction was 96.5 percent complete. -
l I
l l
l
May 8, 1986-ENCLOSURE 7 l I
1 STATUS OF INSPECTIONS REQUIRED BY MC 2512, MC 2513, AND MC 2514 All modules in the Regional inspection program will be. completed to support the 1
projected fuel load date. ,-
I MC 2512 Procedure Percent Number Complete Resp. Title 50076 8 90 MPS Safety-Related . Components II -
Review of Quality Records 50095 B 60 MPS Spent Fuel Storage Racks - Observa- i tion of Work and Work Activities 50100 8 90 MPS Safety-Related Heating, Ventilation, and Air Conditioning (HVAC) Systems 52055 50 PSS Instrumentation (Components and Systems I) - Review of Quality Records l
e .
(
s e
,s Enclosure'7 2 55093 B 0 MPS Reactor Vessel Internals (Welding) -
Observation of Welding Activities 1
55186 8 90 MPS Other Safety-Related . Piping - Weld Heat Treatment i First Inspection Second Inspection 1l 57050 32 MPS Visual. Examination, Procedure j Review / Work, Observation / Record Review 64053 8 80 PSS Fire Loop Installation
.l.
i 11
's l' ,
i l
Enclosure ~7 3 ,
MC 2513
)
i Procedure Percent l-
' Number Complete Resp. Title General 35301 80 QAS Preoperational Testing Quality Assurance-35740 8 50 QAS QA Program - QA/QC Administrative 35741 B 0 QAS QA Program - Audits q 35742 B 50 QAS QA Program - Document Control 35743 0 0PS QA Program - Maintenance 35744 8 30 Q A S. QA Program - Design Changes and Modification 35745 B 30 QAS QA Program - Surveillance Testing and .j Calibration Control .i 35746 B 50 QAS QA. Program - Procurement Control 35747 B 50 QAS QA Program - Receipt, Storage, and l' Handling of Equipment and Materials c________-__:_-___-__--___-__:. ._-_ __-_ _ . _ . __ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _
Enclosure 7 4 35748 8 70 QAS QA Program - Records ;
35749 B 50 QAS QA Program - Tests and Experiments 1 i
35750 30 QAS QA Program - Test and Measurement Equipment ,
36301 8 80 RI Operational Staffing l
37301 80 RI Comparison of As-Built Plant to FSAR Description l
39301 B 0 QAS Preoperational Test Records 40301 B 60 RI Safety Committee Activity l 41301 0 0PS Operating Staff Training i
1 :
l 42400 B 0 RI Plant Procedures l
42450 B 0 0PS Operating Procedures 42451 B 0 0PS Maintenance Procedures 42452 B 0 0PS Emergency Procedures l 1 !
l l l
64704 90 PSS Fire Prevention / Protection Program j l
l I
.__--____-_______a
Enclosure 7 5 70300 80 -T P S Preoperational Test Procedure Review-70311 65 TPS Preoperational' Test Procedure Verification 70312 60 TPS Preoperational Test Witnessing
.~
70329 0 TPS Preoperational Test Results Evaluation Verification 70370 B 0 TPS Testing of Pipe Support and Restraint Systems (PWR only in 2513 Program) 70400 0 TPS Preoperational Test Results Evaluation 71301 B 50 0RP Technical Specification Revies). ,
71302 60 RI Preoperational Test Program Implementation-Verification 79501 70 REC Chemistry Controls 79502 70 REC Systems Affecting Chemistry 81038 0 PSEC Records and Reports 81046 0 PSEC Locks, Keys, and Combinations
Enclosure 7 6 81058 20 P$EC Security System Power Supply ;
81062 0 PSEC Lighting 81066 0 PSEC Assessment Aids l
l 81070 0 PSEC Access Control - Personnel 81072 0 PSEC Access Control (Power Reactor) - Packages 81074 0 PSEC Access Control - Vehicles ,
l 81078 10 PSEC Oetection Aids - Protected Areas 81080 0 PSEC Detection Aids - Vital Areas, Material Access Areas, and Controlled Access Areas 81084 0 PSEC Alarm Stations 81401 0 PSEC Plans, Problems and Reviews i
81403 0 PSEC Receipt of New Fuel at Reactor Facilities 81501 0 PSEC General Requirements for Parsonnel 81810 0 PSEC Physical Protection Safeguards Information
Enclosure 7 7 82101 40 EPS Emergency Preparedness - Preoperational Inspection 83522 25 FRP Rad' Protection, Plant Chemistry, Radwaste, and Environmental: Organization and Management Controls 83523 15 FRP Rad Protection, Plant Chemistry, Radwaste, Transportation and Environmental:-
Training and Qualifications 83524 0 FRP External Occupational Exposure Control and Fersonal Dosimetry 83525 15 FRP Internal Exposure Control and Assessment
~
83526 10 FRP Control of Radiation Materials and Containment, Surveys, and Monitoring 83527 50 FRP Facilities and Equipment 85102 B 0 MCA Material Control and Accounting (Reac+or)
Enclosure 7 8 s 1
J Mandatory Test Procedure' Review
- i l 70304 B 60 TPS. Engineered Safety Features Test - i 1
Preoperational Test Procedure Review 70305 B 80 TPS Reactor Protection System Test -
Preoperational Test Procedure Review 70306 B 0 TPS Loss of Offsite Power Test -
Preoperational Test Procedure Review Mandatory Test Witnessing 70315 B 30 TPS Engineered Safety Features Test:-
Preoperational Test Witnessing 70316 B 0 TPS Loss of Offsite Power Test -
Preoperational Test Witnessing l
70317 8 20 TPS Reactor Protection System Test - ;
i Preoperational Test Witnessing
Enclosure 7 9 1
i i
Mandatory Test Result Evaluation l.
70322 B 0 TPS Preoperational Test Results Evaluation -
ESF 70323 0 TPS Preoperational Test R~esults Evaluation -
(Containment Integrated Leak Rate Test) 70324 B 0 TPS Preoperational Test Results Evaluation -
Hot Functional Testing (PWR only in 2513 Program) 70325 B 0 TPS Preoperational Test Results Evaluation -
Reactor Protection System i
70326 B 0 TPS Preoperational Test Results Evaluation -
Loss of Offsite Power i
i j
l
Enclosure 7 10 l
MC E514 Procedure Percent Number Complete Resp. Title l
35501 50 QAS QA fca the Startup Test Program 60502 C 0 RI Fuel Inspection, Assembly, and Storage 72300 0 TPS Startup Test Procedure Review (Reference Procedura) l 72400 B 0 TPS Overall Startup Test Program 72500 B 0 TPS Initial Fuel Loading Procedure l
l l
l 72564 B 0 TPS Precritical Test Procedure Review (Protective Trip Circuit or Rod Drop Measurement) 72566 B 0 TPS Precritical Test Procedure Review (RCS Leak Test or Pressurizer Effectiveness) l 72570 B 0 TPS Initial Criticality Procedure Review
4 Enclosure 7 . 11 1
72572 B 0 TPS Low Power Test Procedure Review (Moderator Temperature Coefficient and Boron Worth or Control Rod and Pseudo Rod Ejection Worth) 72576'B 0 TPS Power Ascension Test Procedure Review (Natural Circulation or Power Reactivity Coefficient Measurement) 72578 B 0 TPS Power Ascension Test Procedure Review (Evaluation of Core Performance) 72580 B 0 TPS Power Ascension Test Procedure Review (Turbine Trip or Generator Trip) 72582 B D TPS Power Ascension Test Procedure Review - !
l Loss of Offsite Power (Group A) )
)
72583 B 0 TPS Power Ascension Test Proc' dure Review -
i Shutdown from Outside Control Room (Group B) 72584 B 0 TPS Power Ascension Test Procedure Review -
Evaluation of Flux Asymmetry or Pseudo Rod Ejection Test