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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20235B3081987-09-21021 September 1987 Responds to FOIA Request for Documents,Including AEC to ACRS Forwarding Safety Evaluation Re Zimmer.App a Documents Cannot Be Located.App B Documents in Pdr.App C & D Documents Withheld (Ref 10CFR2.790) ML20235M4251987-07-13013 July 1987 Partial Response to FOIA Request for Documents Re Acrs. Forwards Documents for Categories One & Three of FOIA Request.Review of 21 Addl ACRS Documents Continuing ML20126L3111985-07-22022 July 1985 Provides Further Update to 840330 Submission Re Soil Erosion Control & Stabilization Projects Per Insp Rept 50-363/80-02. Revegetation of Banks of Oyster Creek Divided Into Two Portions,W/Eastern Portion Completed in 1984 ML20087P5531984-04-0202 April 1984 Forwards Responses to 840307 Questions Re full-term OL Conversion Environ Review. Effects of Salt Drift on Land Dwelling Vertebrates & Terrestrial Environ Program Annual Rept,Mar 1978 - Feb 1979 Encl ML20084M2941984-03-30030 March 1984 Updates 820728 Response to NRC Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions: Stabilization & Revegetation of Dredge Spoil Slope North of Firepond Completed on 830615 ML20077J0861983-07-20020 July 1983 Forwards Amended Complaint Filed in New Jersey Middlesex Superior Court by Jf Laird,Et Al & Companion Suit Filed by M Ginda & B Keene,Et Al Re Alleged Injuries Resulting from Identical Radiation Exposures ML20083P0791983-01-20020 January 1983 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Soil Erosion Control Project at Barge Unloading Facility Completed ML20076B8331982-10-0404 October 1982 Forwards Info Resolving 14 Tech Spec Open Items Discussed at 820913 meeting.Marked-up Tech Specs Encl IR 05000363/19800021982-08-0909 August 1982 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in IE Insp Rept 50-363/80-02 ML20062H7921982-07-28028 July 1982 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/82-02.Corrective Actions:Soil Stabilization Work Began 820504 & Should Be Complete by 820830 ML20004C7751981-04-23023 April 1981 FOIA Request for Psar,Drawings & Specs Re Facility ML20003G3121981-02-27027 February 1981 Responds to NRC 810203 Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Slope to Be Regraded & Contoured to Decrease Erosion Potential & Amount of Concentrated Rainwater Runoff Washing Slope ML20003A8131981-02-0505 February 1981 Submits Fee for Class III Request Re Delay on One Fire Protection Mod ML20003A9041981-02-0404 February 1981 Responds to NRC 810114 Ltr Re SEP Lead Topic Approach Proposed by SEP Owners Group.Licensee May Not Have Adequate Time to Comment on Safety Evaluation.Written Notification Will Be Provided to Request Addl Time ML19327A3271980-07-14014 July 1980 Informs That IE Bulletins,Circulars & Notices Requiring Review &/Or Response for Facility Are on Hold Due to Postponement of Const Activities.Current Action Files Maintained.Schedule of Responses Will Be Forwarded ML19309D0151980-04-0303 April 1980 Forwards Supplementary Financial Info in Support of TMI-1 Restart Proceedings ML20126D4901980-03-21021 March 1980 Responds to & 800104 Petition to NRC for Public Hearing Re Application for Extension of Cp.Opportunity for Public Hearing Should Be Afforded.Fr Notice of Opportunity Will Be Forwarded Upon Publication ML19320C8141980-03-11011 March 1980 Requests Documents Containing Info Needed for Fuel Cost Study ML19322E6141980-03-11011 March 1980 Responds to IE Bulletin 80-03 Re Visual Insps of Charcoal Adsorber Cells.Equipment of This Type Has Not Been Purchased to Date ML19296E0101980-03-0505 March 1980 Responds to IE Bulletin 79-28 Re Replacement of Top Cover Gaskets on Stem Mounted Limit Switches.Namco EA180 Switches Not Installed in safety-related Equipment Inside or Outside Containment.Assigned Electrical Equipment Being Purchased ML19294B1421980-02-20020 February 1980 Responds to NRC 791226 Ltr Re Estimated Evacuation Time for Plume Exposure Pathway Around Util.Evacuation Time Essentially Same as Oyster Creek,Submitted on 800131. Evacuation Time Estimate of 13.9-h Conservative ML19305C0101980-01-25025 January 1980 Opposes Protracted & Expensive Study of Jcp&L Financial Condition,W/Followup Hearings & Court Battles.Study Would Block Constructive Activity for Yrs.Consumers Will Pay for Delays.Ltr Dtd 800125 to Nj Ofc of Public Advocate Encl ML19257C1711979-11-28028 November 1979 Responds to NRC 791026 Ltr Re Violation Noted in IE Insp Rept 50-363/79-08.Corrective Actions:Venting of Air Bldg Per FSP-1-12,Revision 1,immediately Reinstituted.Field Personnel Instructed to Follow All Approved Procedures Until Revised ML19256F2701979-11-14014 November 1979 Responds to IE Bulletin 79-25, Reactor Trips at Turkey Point Units 3 & 4. No Electrical Equipment Purchased W/ Installed Westinghouse Bfd Relays.Will Request Ae to Identify Type Relays If Bfd Relays Selected ML19256E8251979-11-0707 November 1979 Requests Expansion of Environ Monitoring Program to Include Intensive Mortality Studies of Impinged & Entrained Organisms & Reduced Efforts Re Species Composition & Abundance Sampling ML19210D7121979-10-22022 October 1979 Responds to IE Bulletin 79-24, Frozen Lines. Heat Tracing & Freeze Protection Sys Design Incomplete ML19309H0281979-10-22022 October 1979 Requests Info Re Encl Freeholder RA Gasser 791009 Ltr Discussing s Van Ness Request to Suspend CP ML19254E8341979-09-28028 September 1979 Responds to IE Bulletin 79-23.Emergency Diesel Generator Field Exciter Transformer Not Yet Purchased.When Equipment Is Purchased,Util Will Ensure Design & Testing Meets Items 1 & 2 of Bulletin ML19254D1331979-09-27027 September 1979 Notifies That De Facto Continuation of CP Has Served to Exempt Facility from Complying W/Most up-to-date Safety Sys. Requests Public Hearings Re Safety Issues & Financial Qualifications ML19249D8641979-09-20020 September 1979 Responds to 790821 Ltr Re QA Program for Preservation of safety-related Equipment,Components & Structures During Suspension of Const Activities.Program Will Be in Accordance W/General Requirements of QA Plan ML19254E0631979-09-20020 September 1979 Responds to NRC 790823 Ltr Re Violations Noted in IE Insp Rept 50-363/79-07.Corrective Actions:Preventative Svc & Storage Program Procedures & QA Surveillance Program Procedures Revised ML19249D5201979-08-24024 August 1979 Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Facility Design Currently Employs Vertical Turbine Pumps in Nuclear Svc Water Sys only.As-built Vendor Data Not Yet Available ML20126C5091979-08-16016 August 1979 Opposes Restart of TMI-1,const of Nuclear Plants in Nj & Nuclear Accidents Due to Health Hazards & Risks to Public Safety ML19242A7021979-07-30030 July 1979 Requests Deferment of NRC Action on 780831 Request for Extension of Facility Completion Date.Financial Effects Stemming from TMI-2 Incident Will Preclude Recommencement of Const ML19249A4981979-07-30030 July 1979 Responds to IE Bulletins 79-02 & 79-02 Revision 1,re Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.Pipe Support Base Plate Designs Are Not in Use at Plant ML19242C7061979-07-30030 July 1979 Responds to IE Bulletin 79-14 Re Seismic Analysis for as-built safety-related Piping Sys.No safety-related Piping Sys at Plant ML19225A8601979-07-13013 July 1979 Confirms 790713 Telcon Requesting Summary of NRC Meeting W/Util Re Renewal of Facility CP ML19242B2051979-06-29029 June 1979 Forwards C-E 790608 Ltr Responding to IE Bulletins 78-12, 12A & 12B Re Atypical Weld Matl in Reactor Pressure Vessel Welds ML19242B2921979-06-25025 June 1979 Responds to IE Bulletin 79-11 Re Use of Westinghouse DB-50 & DB-75 Circuit Breakers in safety-related Sys.No Circuit Breakers of This Type Have Been Purchased ML19242B2141979-06-0808 June 1979 Forwards C-E Rept, Info Requested by IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, & Certification That All Matls Used in Reactor Vessel Fabrication Are Discussed in Rept ML19241A7901979-06-0606 June 1979 Responds to IE Bulletin 79-07.Version of Adlpipe Computer Program Which Includes Algebraic Summation Technique Has Been Used for Final Design of Support for Containment Spray Sys ML19246B9371979-06-0606 June 1979 Partially Responds to IE Bulletin 78-12B Re Atypical Weld matl.C-E Will Submit Generic Rept to NRC by 790608.Final Response Will Be Provided by 790629 ML19242B4201979-05-29029 May 1979 Responds to IE Bulletin 79-03 Re Weld Defects in 304 or 312 Stainless Steel Pipe Spools.Spools Used in Containment Penetrations M-43 & M-44.Corrective Actions:Welds Radiographed & Defects Repaired ML19289F4581979-05-0101 May 1979 Responds to IE Bulletin 79-04.Swing Check Valves Not Installed in Facility ML19289F4571979-05-0101 May 1979 Responds to IE Bulletin 79-09.No GE Type AK-2 Circuit Breakers Purchased to Date ML19289F6141979-04-20020 April 1979 Responds to NRC 790312 Ltr Re Violations Noted in IE Insp Rept 50-363/79-02.Corrective Actions:Initiation of Program for Daily Monitoring of Equipment Pressurized W/Inert Gas ML19256F4131979-04-0909 April 1979 Notifies of Concern Over Use of Nuclear Generation & Operating Similarities in Design of TMI-2 & Other Nuclear Units.Requests Meeting W/Nrc to Identify Strategy to Reduce Probability of TMI-incident at Facility ML19289F2061979-03-15015 March 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Rept 50-363/78-15.Corrective Actions:Theodolite Was Serviced & Two Tachometers Sent for Recalibr ML20104A7271979-03-0505 March 1979 Forwards Design Info,Submittal 2,Structural Reorientation, W/Current Design Features Reflecting New Licensing Concerns of post-CP Period 1999-06-25
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20126L3111985-07-22022 July 1985 Provides Further Update to 840330 Submission Re Soil Erosion Control & Stabilization Projects Per Insp Rept 50-363/80-02. Revegetation of Banks of Oyster Creek Divided Into Two Portions,W/Eastern Portion Completed in 1984 ML20087P5531984-04-0202 April 1984 Forwards Responses to 840307 Questions Re full-term OL Conversion Environ Review. Effects of Salt Drift on Land Dwelling Vertebrates & Terrestrial Environ Program Annual Rept,Mar 1978 - Feb 1979 Encl ML20084M2941984-03-30030 March 1984 Updates 820728 Response to NRC Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions: Stabilization & Revegetation of Dredge Spoil Slope North of Firepond Completed on 830615 ML20077J0861983-07-20020 July 1983 Forwards Amended Complaint Filed in New Jersey Middlesex Superior Court by Jf Laird,Et Al & Companion Suit Filed by M Ginda & B Keene,Et Al Re Alleged Injuries Resulting from Identical Radiation Exposures ML20083P0791983-01-20020 January 1983 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Soil Erosion Control Project at Barge Unloading Facility Completed ML20076B8331982-10-0404 October 1982 Forwards Info Resolving 14 Tech Spec Open Items Discussed at 820913 meeting.Marked-up Tech Specs Encl ML20062H7921982-07-28028 July 1982 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/82-02.Corrective Actions:Soil Stabilization Work Began 820504 & Should Be Complete by 820830 ML20004C7751981-04-23023 April 1981 FOIA Request for Psar,Drawings & Specs Re Facility ML20003G3121981-02-27027 February 1981 Responds to NRC 810203 Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Slope to Be Regraded & Contoured to Decrease Erosion Potential & Amount of Concentrated Rainwater Runoff Washing Slope ML20003A8131981-02-0505 February 1981 Submits Fee for Class III Request Re Delay on One Fire Protection Mod ML20003A9041981-02-0404 February 1981 Responds to NRC 810114 Ltr Re SEP Lead Topic Approach Proposed by SEP Owners Group.Licensee May Not Have Adequate Time to Comment on Safety Evaluation.Written Notification Will Be Provided to Request Addl Time ML19327A3271980-07-14014 July 1980 Informs That IE Bulletins,Circulars & Notices Requiring Review &/Or Response for Facility Are on Hold Due to Postponement of Const Activities.Current Action Files Maintained.Schedule of Responses Will Be Forwarded ML19309D0151980-04-0303 April 1980 Forwards Supplementary Financial Info in Support of TMI-1 Restart Proceedings ML19320C8141980-03-11011 March 1980 Requests Documents Containing Info Needed for Fuel Cost Study ML19322E6141980-03-11011 March 1980 Responds to IE Bulletin 80-03 Re Visual Insps of Charcoal Adsorber Cells.Equipment of This Type Has Not Been Purchased to Date ML19296E0101980-03-0505 March 1980 Responds to IE Bulletin 79-28 Re Replacement of Top Cover Gaskets on Stem Mounted Limit Switches.Namco EA180 Switches Not Installed in safety-related Equipment Inside or Outside Containment.Assigned Electrical Equipment Being Purchased ML19294B1421980-02-20020 February 1980 Responds to NRC 791226 Ltr Re Estimated Evacuation Time for Plume Exposure Pathway Around Util.Evacuation Time Essentially Same as Oyster Creek,Submitted on 800131. Evacuation Time Estimate of 13.9-h Conservative ML19305C0101980-01-25025 January 1980 Opposes Protracted & Expensive Study of Jcp&L Financial Condition,W/Followup Hearings & Court Battles.Study Would Block Constructive Activity for Yrs.Consumers Will Pay for Delays.Ltr Dtd 800125 to Nj Ofc of Public Advocate Encl ML19257C1711979-11-28028 November 1979 Responds to NRC 791026 Ltr Re Violation Noted in IE Insp Rept 50-363/79-08.Corrective Actions:Venting of Air Bldg Per FSP-1-12,Revision 1,immediately Reinstituted.Field Personnel Instructed to Follow All Approved Procedures Until Revised ML19256F2701979-11-14014 November 1979 Responds to IE Bulletin 79-25, Reactor Trips at Turkey Point Units 3 & 4. No Electrical Equipment Purchased W/ Installed Westinghouse Bfd Relays.Will Request Ae to Identify Type Relays If Bfd Relays Selected ML19256E8251979-11-0707 November 1979 Requests Expansion of Environ Monitoring Program to Include Intensive Mortality Studies of Impinged & Entrained Organisms & Reduced Efforts Re Species Composition & Abundance Sampling ML19210D7121979-10-22022 October 1979 Responds to IE Bulletin 79-24, Frozen Lines. Heat Tracing & Freeze Protection Sys Design Incomplete ML19309H0281979-10-22022 October 1979 Requests Info Re Encl Freeholder RA Gasser 791009 Ltr Discussing s Van Ness Request to Suspend CP ML19254E8341979-09-28028 September 1979 Responds to IE Bulletin 79-23.Emergency Diesel Generator Field Exciter Transformer Not Yet Purchased.When Equipment Is Purchased,Util Will Ensure Design & Testing Meets Items 1 & 2 of Bulletin ML19254D1331979-09-27027 September 1979 Notifies That De Facto Continuation of CP Has Served to Exempt Facility from Complying W/Most up-to-date Safety Sys. Requests Public Hearings Re Safety Issues & Financial Qualifications ML19249D8641979-09-20020 September 1979 Responds to 790821 Ltr Re QA Program for Preservation of safety-related Equipment,Components & Structures During Suspension of Const Activities.Program Will Be in Accordance W/General Requirements of QA Plan ML19254E0631979-09-20020 September 1979 Responds to NRC 790823 Ltr Re Violations Noted in IE Insp Rept 50-363/79-07.Corrective Actions:Preventative Svc & Storage Program Procedures & QA Surveillance Program Procedures Revised ML19249D5201979-08-24024 August 1979 Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Facility Design Currently Employs Vertical Turbine Pumps in Nuclear Svc Water Sys only.As-built Vendor Data Not Yet Available ML20126C5091979-08-16016 August 1979 Opposes Restart of TMI-1,const of Nuclear Plants in Nj & Nuclear Accidents Due to Health Hazards & Risks to Public Safety ML19242C7061979-07-30030 July 1979 Responds to IE Bulletin 79-14 Re Seismic Analysis for as-built safety-related Piping Sys.No safety-related Piping Sys at Plant ML19242A7021979-07-30030 July 1979 Requests Deferment of NRC Action on 780831 Request for Extension of Facility Completion Date.Financial Effects Stemming from TMI-2 Incident Will Preclude Recommencement of Const ML19249A4981979-07-30030 July 1979 Responds to IE Bulletins 79-02 & 79-02 Revision 1,re Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.Pipe Support Base Plate Designs Are Not in Use at Plant ML19225A8601979-07-13013 July 1979 Confirms 790713 Telcon Requesting Summary of NRC Meeting W/Util Re Renewal of Facility CP ML19242B2051979-06-29029 June 1979 Forwards C-E 790608 Ltr Responding to IE Bulletins 78-12, 12A & 12B Re Atypical Weld Matl in Reactor Pressure Vessel Welds ML19242B2921979-06-25025 June 1979 Responds to IE Bulletin 79-11 Re Use of Westinghouse DB-50 & DB-75 Circuit Breakers in safety-related Sys.No Circuit Breakers of This Type Have Been Purchased ML19242B2141979-06-0808 June 1979 Forwards C-E Rept, Info Requested by IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, & Certification That All Matls Used in Reactor Vessel Fabrication Are Discussed in Rept ML19241A7901979-06-0606 June 1979 Responds to IE Bulletin 79-07.Version of Adlpipe Computer Program Which Includes Algebraic Summation Technique Has Been Used for Final Design of Support for Containment Spray Sys ML19246B9371979-06-0606 June 1979 Partially Responds to IE Bulletin 78-12B Re Atypical Weld matl.C-E Will Submit Generic Rept to NRC by 790608.Final Response Will Be Provided by 790629 ML19242B4201979-05-29029 May 1979 Responds to IE Bulletin 79-03 Re Weld Defects in 304 or 312 Stainless Steel Pipe Spools.Spools Used in Containment Penetrations M-43 & M-44.Corrective Actions:Welds Radiographed & Defects Repaired ML19289F4571979-05-0101 May 1979 Responds to IE Bulletin 79-09.No GE Type AK-2 Circuit Breakers Purchased to Date ML19289F4581979-05-0101 May 1979 Responds to IE Bulletin 79-04.Swing Check Valves Not Installed in Facility ML19289F6141979-04-20020 April 1979 Responds to NRC 790312 Ltr Re Violations Noted in IE Insp Rept 50-363/79-02.Corrective Actions:Initiation of Program for Daily Monitoring of Equipment Pressurized W/Inert Gas ML19256F4131979-04-0909 April 1979 Notifies of Concern Over Use of Nuclear Generation & Operating Similarities in Design of TMI-2 & Other Nuclear Units.Requests Meeting W/Nrc to Identify Strategy to Reduce Probability of TMI-incident at Facility ML19289F2061979-03-15015 March 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Rept 50-363/78-15.Corrective Actions:Theodolite Was Serviced & Two Tachometers Sent for Recalibr ML20104A7271979-03-0505 March 1979 Forwards Design Info,Submittal 2,Structural Reorientation, W/Current Design Features Reflecting New Licensing Concerns of post-CP Period ML19274D8901979-01-16016 January 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Repts 50-363/78-15.Corrective Actions:Equipment Was Recalibr & Validating Test Data Taken Following Expiration Date ML19270F2101978-12-20020 December 1978 Responds to NRC 781116 Ltr Re Violation Noted in IE Insp Rept 50-363/78-13.Corrective Actions:Procedure for Placement & Curing of Concrete Revised to Include Quantitative & Qualitative Acceptance Criteria ML20147C1231978-11-13013 November 1978 Responds to 781017 NRC Ltr Re Violation Noted in Inspec Rept 50-363/78-12.Corrective Actions:Personnel Reinspected & Retested;Inspector Assigned to Inspect Status of Concrete Curing ML20150C3901978-11-13013 November 1978 Forwards Statement by RA Gasser Re Proposed Salt Water Cooling Tower at Subj Facil 1999-06-25
[Table view] Category:UTILITY TO NRC
MONTHYEARML20126L3111985-07-22022 July 1985 Provides Further Update to 840330 Submission Re Soil Erosion Control & Stabilization Projects Per Insp Rept 50-363/80-02. Revegetation of Banks of Oyster Creek Divided Into Two Portions,W/Eastern Portion Completed in 1984 ML20087P5531984-04-0202 April 1984 Forwards Responses to 840307 Questions Re full-term OL Conversion Environ Review. Effects of Salt Drift on Land Dwelling Vertebrates & Terrestrial Environ Program Annual Rept,Mar 1978 - Feb 1979 Encl ML20084M2941984-03-30030 March 1984 Updates 820728 Response to NRC Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions: Stabilization & Revegetation of Dredge Spoil Slope North of Firepond Completed on 830615 ML20083P0791983-01-20020 January 1983 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Soil Erosion Control Project at Barge Unloading Facility Completed ML20076B8331982-10-0404 October 1982 Forwards Info Resolving 14 Tech Spec Open Items Discussed at 820913 meeting.Marked-up Tech Specs Encl ML20062H7921982-07-28028 July 1982 Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-363/82-02.Corrective Actions:Soil Stabilization Work Began 820504 & Should Be Complete by 820830 ML20003G3121981-02-27027 February 1981 Responds to NRC 810203 Ltr Re Violations Noted in IE Insp Rept 50-363/80-02.Corrective Actions:Slope to Be Regraded & Contoured to Decrease Erosion Potential & Amount of Concentrated Rainwater Runoff Washing Slope ML20003A8131981-02-0505 February 1981 Submits Fee for Class III Request Re Delay on One Fire Protection Mod ML20003A9041981-02-0404 February 1981 Responds to NRC 810114 Ltr Re SEP Lead Topic Approach Proposed by SEP Owners Group.Licensee May Not Have Adequate Time to Comment on Safety Evaluation.Written Notification Will Be Provided to Request Addl Time ML19327A3271980-07-14014 July 1980 Informs That IE Bulletins,Circulars & Notices Requiring Review &/Or Response for Facility Are on Hold Due to Postponement of Const Activities.Current Action Files Maintained.Schedule of Responses Will Be Forwarded ML19309D0151980-04-0303 April 1980 Forwards Supplementary Financial Info in Support of TMI-1 Restart Proceedings ML19322E6141980-03-11011 March 1980 Responds to IE Bulletin 80-03 Re Visual Insps of Charcoal Adsorber Cells.Equipment of This Type Has Not Been Purchased to Date ML19296E0101980-03-0505 March 1980 Responds to IE Bulletin 79-28 Re Replacement of Top Cover Gaskets on Stem Mounted Limit Switches.Namco EA180 Switches Not Installed in safety-related Equipment Inside or Outside Containment.Assigned Electrical Equipment Being Purchased ML19294B1421980-02-20020 February 1980 Responds to NRC 791226 Ltr Re Estimated Evacuation Time for Plume Exposure Pathway Around Util.Evacuation Time Essentially Same as Oyster Creek,Submitted on 800131. Evacuation Time Estimate of 13.9-h Conservative ML19257C1711979-11-28028 November 1979 Responds to NRC 791026 Ltr Re Violation Noted in IE Insp Rept 50-363/79-08.Corrective Actions:Venting of Air Bldg Per FSP-1-12,Revision 1,immediately Reinstituted.Field Personnel Instructed to Follow All Approved Procedures Until Revised ML19256F2701979-11-14014 November 1979 Responds to IE Bulletin 79-25, Reactor Trips at Turkey Point Units 3 & 4. No Electrical Equipment Purchased W/ Installed Westinghouse Bfd Relays.Will Request Ae to Identify Type Relays If Bfd Relays Selected ML19256E8251979-11-0707 November 1979 Requests Expansion of Environ Monitoring Program to Include Intensive Mortality Studies of Impinged & Entrained Organisms & Reduced Efforts Re Species Composition & Abundance Sampling ML19210D7121979-10-22022 October 1979 Responds to IE Bulletin 79-24, Frozen Lines. Heat Tracing & Freeze Protection Sys Design Incomplete ML19254E8341979-09-28028 September 1979 Responds to IE Bulletin 79-23.Emergency Diesel Generator Field Exciter Transformer Not Yet Purchased.When Equipment Is Purchased,Util Will Ensure Design & Testing Meets Items 1 & 2 of Bulletin ML19249D8641979-09-20020 September 1979 Responds to 790821 Ltr Re QA Program for Preservation of safety-related Equipment,Components & Structures During Suspension of Const Activities.Program Will Be in Accordance W/General Requirements of QA Plan ML19254E0631979-09-20020 September 1979 Responds to NRC 790823 Ltr Re Violations Noted in IE Insp Rept 50-363/79-07.Corrective Actions:Preventative Svc & Storage Program Procedures & QA Surveillance Program Procedures Revised ML19249D5201979-08-24024 August 1979 Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Facility Design Currently Employs Vertical Turbine Pumps in Nuclear Svc Water Sys only.As-built Vendor Data Not Yet Available ML19249A4981979-07-30030 July 1979 Responds to IE Bulletins 79-02 & 79-02 Revision 1,re Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.Pipe Support Base Plate Designs Are Not in Use at Plant ML19242C7061979-07-30030 July 1979 Responds to IE Bulletin 79-14 Re Seismic Analysis for as-built safety-related Piping Sys.No safety-related Piping Sys at Plant ML19242A7021979-07-30030 July 1979 Requests Deferment of NRC Action on 780831 Request for Extension of Facility Completion Date.Financial Effects Stemming from TMI-2 Incident Will Preclude Recommencement of Const ML19242B2051979-06-29029 June 1979 Forwards C-E 790608 Ltr Responding to IE Bulletins 78-12, 12A & 12B Re Atypical Weld Matl in Reactor Pressure Vessel Welds ML19242B2921979-06-25025 June 1979 Responds to IE Bulletin 79-11 Re Use of Westinghouse DB-50 & DB-75 Circuit Breakers in safety-related Sys.No Circuit Breakers of This Type Have Been Purchased ML19241A7901979-06-0606 June 1979 Responds to IE Bulletin 79-07.Version of Adlpipe Computer Program Which Includes Algebraic Summation Technique Has Been Used for Final Design of Support for Containment Spray Sys ML19246B9371979-06-0606 June 1979 Partially Responds to IE Bulletin 78-12B Re Atypical Weld matl.C-E Will Submit Generic Rept to NRC by 790608.Final Response Will Be Provided by 790629 ML19242B4201979-05-29029 May 1979 Responds to IE Bulletin 79-03 Re Weld Defects in 304 or 312 Stainless Steel Pipe Spools.Spools Used in Containment Penetrations M-43 & M-44.Corrective Actions:Welds Radiographed & Defects Repaired ML19289F4571979-05-0101 May 1979 Responds to IE Bulletin 79-09.No GE Type AK-2 Circuit Breakers Purchased to Date ML19289F4581979-05-0101 May 1979 Responds to IE Bulletin 79-04.Swing Check Valves Not Installed in Facility ML19289F6141979-04-20020 April 1979 Responds to NRC 790312 Ltr Re Violations Noted in IE Insp Rept 50-363/79-02.Corrective Actions:Initiation of Program for Daily Monitoring of Equipment Pressurized W/Inert Gas ML19289F2061979-03-15015 March 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Rept 50-363/78-15.Corrective Actions:Theodolite Was Serviced & Two Tachometers Sent for Recalibr ML19274D8901979-01-16016 January 1979 Responds to NRC 781214 Ltr Re Violations Noted in IE Insp Repts 50-363/78-15.Corrective Actions:Equipment Was Recalibr & Validating Test Data Taken Following Expiration Date ML19270F2101978-12-20020 December 1978 Responds to NRC 781116 Ltr Re Violation Noted in IE Insp Rept 50-363/78-13.Corrective Actions:Procedure for Placement & Curing of Concrete Revised to Include Quantitative & Qualitative Acceptance Criteria ML20147C1231978-11-13013 November 1978 Responds to 781017 NRC Ltr Re Violation Noted in Inspec Rept 50-363/78-12.Corrective Actions:Personnel Reinspected & Retested;Inspector Assigned to Inspect Status of Concrete Curing ML20150B6791978-09-25025 September 1978 Responds to 780822 NRC Ltr Re Violations Noted in Inspec Rept 50-363/78-10.Corrective actions:3 Training Sessions Have Been Held w/Morrison-Knudsen Quality Dept Addressing Areas of Violation ML20049A1131978-08-31031 August 1978 Requests Extension of Earliest & Lastest Completion Dates for CPPR-96 from 770404 to 781004 & 830201 to 850201, Respectively 1985-07-22
[Table view] |
Text
__________-____ -
. *4 . . ,
( ) {. File: 2421.10
. hc- 7.f 4""
() Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Nkyristown. New Jersey 07960 (201)455-820)
November 13, 1978 v
Mr. Boyce H. Grier, Director Office of Inspection 5 Enforcement, Region I U.S. Nuclear Regulatory Commission 631 Park Avenut King of Prussia, PA 19406
Dear Mr. Grier:
SUBJECT:
LICENSE NUMBER CPPR-96 INSPECTION NUMBER 78-12 DOCKET NIIMRER 50-363 This letter responds to the subject inspection report which presents an infraction uncovered by Mr. A. A. Varela during his inspection Sep-tember 12-15, 1978. Below is our response to the infraction cited in the subject inspection report.
Infraction 10 CFR 50 Appendix B, Criterion V states, in part, that " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings .
and shall be accomplished in accordance with these instructions, drawings, and procedures ...."
The licensee's Quality Assurance Plan, Revision 9, Section 5.0 states, in part, the Forked River Unit Quality Assurance Program requires that:
" Quality related activities be prescribed by appropriately documented instructions, procedures and drawings", and "The activities be accomplished in accordance with such documents.
- 1. Morrison-Knudsen (M-K) Construction Procedure CP-11-FR, Revision 1,
" Placement and curing of Concrete",Section VI.N Preservation of Moisture, requirer:
For concrete surfaces not in contact with fo .s, one of the following procedures as applicable s' .11 be r.pplied immediately after completion of placement and finishing:
(a) Ponding or continuous sprinkling.
(b) Application of absorbtive mats or fabric kept
-continuously wet.
Jersey Central Power & Light Company is a Member of the Genera! Pubhc Utitres System
Y . .
. *Mr..Boyc'e H. Grier November 13, 1978 (c) Application of sand kept continuously wet.
(d) Application of an approved waterproof sheet material.
(e) Application of other moisture-retaining ,
covering as approved or in specification.
(f) Application of an approved membrane curing compound.
(g) Continuous application of steam or mist spray.
Ccntrary to the above, containment basemat concrete placements number LSK 104-B and 103-A completed on the afternoon and evening of Sep-tember 11, 1978 were observed on the afternoon and evening of Sep-tember 13, 1978 to have no application of absorbtive cover and/or water on horizontal surfaces. On the morning of September 14, 1978, approximately 30% of horizontal finished surface and construction joints were dry when hand tested. On the morning of September 14, 1978, vertical forms on pour 104-0 were ren.9ved, draped with plastic but not scaled. Vertical concrete at midday was observed to be surface dry and remained without moisture application until late in the afternoon.
- 2. Morrison-Knudsen Construction Procedure CP-11-FR Revision 1,Section XI.C, Inspection and Test Requirements, prescribes:
The Quality Control Inspection will verify that the concrete curing method is properly applied and maintained for the minimum curing period.
Contrary to the above, containment basemat concrete placements LSK 104-B and 103-A completed on the afternoon and evening of September 12, 1978 were ,
not verified by the QC Inspector for adequacy of curing on September 13 and 14, 1978.
Corrective Action Taken
- 1. GPUSC-QA through disposition to Non-Conformance Report No. 0371 directed that M-K " Maintain exposed surfaces (Placements 103-A and 104-B) under wet cure until October 16, 1978."
- 2. M-K personnel were reinspected by GPUSC-QA to the requirements of M-K procedure CP-11-FR with respect to curing requirements and documentation.
M-K's inspector was retested on September 25, 1978 and obtained a grade of 79.5% on a written examination. Based on this,M-K was allowed to continue work in the containment area.
- R Mr: Boyce H. Grier November 13, 1978 Corrective Steps to Avoid Further Infractions As of October 5,1978, a Morrison-Knudsen Inspector has been assigned, full time, to inspect the status of concrete curing and to take and record temperatures. This assignment will be continued until it has been satis-factorily demonstrated that it is no longer required.
Additionally, training sessions were held by M-K on September 25, 1978 and October 12, 1978 on the ACI requirements goveIming the curing of concrete.
This means of additional instruction and training will be continued on a scheduled basis.
Very truly yours, l j l1,h' f :.? :/
Ivan R. Finfrqpk, Jr:
Vice President asb
- " "I W UNITED STATES
- f. . . .% NUCLEAR REGULATORY COMMISslON f " "A ( $ REGION i E 631 PARK AVENUE 7, $p g f ': ,8 KING OF PRUSSI A, PENNSYLVANI A 19406 o,s a ,
- a,e Docket No. 50-363 Jersey Central Power & Light Company ATTN: Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Gentlemen:
Subject:
Inspection 50-363/78-12 This refers to the inspection conducted by Mr. A. A. Varela of this office on September 12-15, 1978, at the Forked River Nuclear Station, l Unit 1. Forked River, New Jersey, of activities authorized by NRC License No. CPPR-96 ard to the discussions of our findings held by Mr.
Varela with Mr. S. Levin of your staff at the conclusion of the inspection.
Areas examined during this inspection are described in the Office of Inspection and Enforcement Inspection Report which is enclosed with this I
letter. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Based on the results of this inspection, it appears that one of your l
activities was not conducted in full compliance with NRC requirements, as set forth in the Notice of Violation, enclosed herewith as Appendix A. This item of noncompliance has been categorized into the levels as described in our correspondence to you dated December 31, 1974. This notice is sent to you pursuant to the provisions of Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations.
Section 2.201 requires you to submit to this office, within twenty (20) days of your receipt of this notice, a written statement or explanation in reply including: (1) corrective steps which have been taken by you and the results achieved; (2) corrective steps which will be taken to avoid further items of noncompliance; and (3) the date when full compliance will be achieved.
l 2 O2 k/
7813.15
Jersey Central Power & Light 2 Company In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room. If this report contains any information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application I within 20 days to this office to withhold such information from public l
disclosu,re. Any such application must be accompanied by an affidavit executed by the owner of the information, which identifies the document or part sought to be withheld, and which contains a statement of reasons which addresses with specificity the items which will be considered by the Commission as listed in subparagraph (b)(4) of Section 2.790. The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit. If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, A
Robert T. Carlson, Chief Reactor Construction and Engineering Support Branch
Enclosures:
- 1. Appendix A, Notice of Violation
- 2. Office of Inspection and Enforcement Inspection Report Number 50-363/78-12 cc w/encis:
M. K. Pastor, Project Manager
O APPENDIX A NOTICE OF VIOLATION Jersey Central Power and Light Company Docket No. 50-363 Based on the results of the NRC inspection conducted on September 12-15, 1978, it appears that one of your activities was not conducted in full compliance with conditions of your NRC Facility License No. CPPR-96 as
.indicateo below. This item is an infraction.
10 CFR 50, Appendix 8, Criterion V, states, in part, that" "Acti-vities affecting quality shall be prescribed by documented instruc-tions, procedures, or drawings...and shall be accomplished in accordance with these instructions, drawings, and procedures. . ."
The licensee's Quality Assurance Plan, Revision 9, Section 5.0 states, in part, the Forked River Unit 1 Quality Assurance Program requires that:
Quality related activities be prescribed by appropriately documented instructions, procedures and drawings," and
. "The activities be accomplished in accordance with such docu-ments."
- 1. Morrisor.-Knudsen Construction Procedure CP-11-FR, Revision 1,
" Placement and Curing of Concrete",Section VI.N, Preservation of Moisture, requires:
For concrete surfaces not in contact with forms one of the following procedures as applicable shall be applied immediately after completion of placement and finishing:
- a. Ponding or continuous sprinkling
- b. Application of absorptive mats or fabric kept continuously wet
- c. Application of sand kept continuously wet
- d. Application of an approved waterproof sheet material 781218-1
a Appendix A 2
- e. Application of other moisture-retaining covering as approved or in specification
- f. Application of an approved membrane curing compound
- g. Continuous application of steam or mist spray Contrary to the above, containment basemat concrete placements number LSK 104-B and 103-A completed on the afternoon and evening of September 12, 1978 were observed on midday September 13 to have no application of absorptive cover and/or water on horizontal surfaces. On the morning of September 14, approximately 30% of horizontal finished surface and construction joints were dry when hand tested. On the morning of September 14, vertical forms on psur 104-B were removed, draped with plastic but not sealed.
Vertical concrete at midday was observed to be surface dry and remained without moisture application until late in afternoon.
- 2. Morrison-Knudsen Construction Procedure Cp-ll-FR, Revision 1, in Section XI.C, Inspection and Test Requirements, prescribes:
l The Quality Control Inspector will verify that the concrete curing method is properly applied and maintained for the minimum curing period.
Contrary to the above, containment basemat concrete placements LSK 104-B and 103-A completed on the afternoon and evening of September 12, were not verified by the QC inspector for adequacy of curi.ig on September 13 and 14.
U.S. NUCLEAR REGULATORY COMMISSION Q OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-363/78-12 Docket No. 50-363 l License No. CPPR-96 Priority --
Category A Licensee: Jersey Central Power and Light Company 260 Cherry Hill Road Parsippany, New Jersey 07054 Facility Name: Forked River Nuclear Station. Unit 1 Inspection at: Forked River, New Jersey Inspection condtreted:] Septembe 2-15, 1978 Inspectors: / /
7 A_ hCR'k'T 2, li76 W. G."Varela, Reactor Inspector date signed date signed date signed Approved by: k/)- M , /d 76 f D. Ebneter, Chief, Engineering Support dats signed Section No. 2, RC&ES Branch Inspection Summary:
Inspection on September 12-15, 1978 (Report No. 50-363/78-12)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of reinforcing steel installation and cadweld splicing for the containment basemat. Concrete mixing, delivery, testing, placement, finishing and curing for containment basemat was observed. The inspector also observed backfill placement, compaction and testing, and reviewed records on maintenarce of de-watering, pressure relief and slope stability of the excavation. A site tour inspection was performed and previously identified unresolved items were reviewed.
The inspection involved 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> onsite by one NRC regional based inspector.
Results: Of the six areas inspected, one item of noncompliance was identified in curing of concrete.
$5 Y 781 Q5 Region I Form 12 (Rev. April 77)
i DETAILS
- 1. Persons Contacted General Public Utilities Service Corporation (GPU)
J. J. Barton, Project Site Manager J. W. Davis, Resident Civil Engineer
- R. F. Fenti, Senior Site QA Auditor J. W. Griest, Project Construction Manager
- S. Levin, Supervisor Site Engineering
- J. C. Thompson, Site Quality Control Supervisor J. E. Wright, Site Quality Assurance Manager Stone and Webster Engineering Corporation (S&W)
J. Adachi, Concrete Testing Site Manager (PTL)
L. Brown, Construction Superintendent S. Deyo, Construction Engineer W. G. Dick, Area Superintendent S. D. Morris. Quality Control Engineer G. Noons, Area Engineer
- B. Officer, Assistant Superintendent of Construction
- K. Platte, Resident Engineer F. Puffer, Quality Control Engineer A. Pir,ter, Quality Control Engineer
- R. L. Wagner, Superintendent of Construction Morrison-Knudsen (M-K)
R. Barnes, Quality Control Engineer R. Colasardo, Soil Test Engineer, (U.S. Testing Company)
N. Corbi, Reinforcing Steel Superintendent L. Grandpre, Construction Superintendent H. Haney, Area Superintendent
- D. Kivisto, Assistant Project Manager D. Richards, Quality Control Engineer
- R. Stauber, Site Quality Assurance Manager D. Sleeper, Quality Control Cadwel Inspector
3 Burns and Roe Inc. (B&R)
T. Hayes, Geotechnical Engineer S. Lazorchak, Site Field Engineer E. Zisman, Senior Geotechnical Engineer Eastern Shore Transit Mix (EST)
R. Johnson, Quality Control Manager V. Nagee, Quality Control Engineer F. DeCessaro, Batch Plant Operator A. Vendrasco, Vice President l
l
- denotes those present at the exit interview.
The inspector also interviewed other licensee and contractor employees during the inspection, including quality control and construction crafts.
- 2. Plant Tour The inspector made a tour of the construction site to observe work activities in progress. The inspector examined work items for any obvious defects or noncompliance with regulatory requirements and for evidence of quality control of the work. Specific activities observed by the inspector included installation and cadwelding of reinforcing steel for the reactor well basemat, placing, compacting and testing of structural backfill, mixing, transporting, testing and placing concrete for the containment basemat and laboratory tensile tests on vertical #18 cadweld splices to qualify operators.
As identified in Paragraph 4 concrete placement practices observed, at start of work on the containment basemat pour, LSK 104-B appearing as poor practice was corrected. Paragraph 5 identifies a noncompliance in post placement concrete curing. Except for these items, other construction site work activities were observed to be without items of noncompliance.
4
- 3. Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (363/78-08-02): Procedure on mechanical splicing of rebar requires corrections for clarity and specificity.
Procedure CP-12-FR on mechanical splicing of reinforcing steel bars was revised by M-K June 21, 1978 and revision number 3 was approved and released for construction on June 26, 1978. The inspector re-viewed CP-12-FR revision 3 and observed specific changes in detail provided adequate clarity. Also additional inspection criteria and forms for quality control documentation are provided.
- 4. Corrective Action Taken in Concrete Placement of Containment Basemat Block LSK 104-8 The inspector observed concrete placement of containment basemat block LSK 104-B shortly after start of the placement at midday September 12, 1978. He observed that method used in depositing concrete from conveyor vertically through about 25' of telescoping plastic drop chutes caused separation of the aggregate from the mortar and scattering of the three-quarter inch, maximum size aggregate. The placement and practice could have caused segregation of the aggregate in the mix. The inspector discussed this with S&W and M-K QC personnel with the result that the concrete placement was delayed. Changes were made to the drop chute to provide a section of chute with reduced diameter to control the concrete velocity at exit, and to extend the chute to deposit concrete as close as possible between rebar to its final position in the forms. Continuation of concrete placement complying with requirements was observed by the inspector to complete block LSK 104-B. No undue scattering of aggregate or segregation was observed in remainder of pour.
- 5. Noncompliance in Concrete Cure of Containment Basemat Blocks LSK 104-8 and 103-A Concrete placements LSK 104-B and 103-A for the containment tendon gallery basemat were completed mid afternoon and evening, respec-tively, September 12, 1978. M-K construction procedure CP-ll-FR, requires in Section VI.N, Preservation of Moisture:
5
- 1. For concrete surfaces not in contact with forms, one of the following procedures as applicable shall be applied immediately after completion of placement and finishing:
- a. Ponding or continuous sprinkling
- b. Application of absorptive mats or fabric kept continuously wet
- c. Application of sand kept continuously wet
- d. Continuous application of steam or mist spray
- e. Application of an approved waterproof sheet material
- f. Application of other moisture-retaining covering as approved or in specification
- g. Application of an approved membrane curing compound The inspector observed on the afternoon of September 12, following completion of concrete placement on pour 104-8 that horizontal con-struction joint areas were not provided with any above methods for moisture preservation or moisture addition. On the morning of September 13 and thoughout that day, moist cure was not applied to pour 104-B or 103-A until late in the afternoon. However, on the morning of September 14 about 30 percent of both areas were surface dry. Vertical wall wooden forms were stripped from 104-8 on the morning of September 14 but plastic sheet covering was not sealed to prevent loss of moisture, and surfaces were dry in the afternoon before water was applied. Additionally, M-K construction procedure CP-11-FR requires in Section XI.C:
"The QC inspector will verify that the concrete curing method is properly applied and maintained for the cure period."
The NRC inspector observed that M-K QC did not verify cure method on pours LSK 104-B and 103-A on September 13 and 14.
/ 6 Failure to provide concrete surfaces not in contact with forms with a method for preservation of moisture immediately after completion of placement and finishing, failure to continuously maintain moisture on concrete, and failure by QC to verify that cure method is pro-perly applied is considered to be in noncompliance with Criterion V of 10 CFR 50, Appendix B. (78-12-01)
- 6. Observation of Concrete Placement of Containment Basemat Block LSK 104 Preplacement Activities for Block LSK 103-A and Rebar Installation.and Cadwelding for Reactor Well Basemat The inspector observed placement preparation and concrete placement of containment basemat blocks LSK 103-A and 104-8 respectively, on September 12, 1978, and QC inspection performed in connection with this work. These activities were inspected for conformance to the following:
Forked River Nuclear Station, Unit 1, PSAR Section V and Appendix SD.
B&R Specification 2700-206, Rev. 6, " Substructure" B&R Specification 2700-202, Rev. 8, " Production and Delivery of Concrete" GPU Specification 202-003, Rev. 3, " Specification for Per-formance of Owners Site Civil Testing"
-- GPU QC Procedure FR-1-10-04, Rev 0, " Site QA/QC Surveillance Procedure" M-K Construction Procedure CP-ll-FR, Rev.1, " Placement and Curing of Concrete" The inspector determined the following activities were accomplished according to applicable specifications, codes, standards and pro-cedures:
7
- a. Placement Preparation for Block LSK 103-A - forms properly secured, tight and clean; rebar and other embedments properly placed, secured, clean and specified distance from forms; preplacement inspection completed prior to concrete placement; construction joints and water stops prepared as specified and/or approved.
- b. Delivery and Placement - proper mix specified and delivered; controlled mixing and delivery time; testing at truck dis-charge properly performed using calibrated equipment; properly controlled concrete remixing in truck when approved water added at truck discharge; adequate crew, equipment and tech-niques prevented segregation; adequate consolidation with tested vibrators; inspection during placement.
- c. Aggregate and Cement Storage - aggregate of different sizes in separated storage bins; cement adequately protected; inspection of all concrete ingredients conforms to requirements for scope and frequency.
- d. Rebar Installation and Cadwelding - number 18S rebar installa-tion for the reactor well basemat block conforms to specifi-cation 206, engineering drawings S745, S746 and S747 and pertinent rebar detail layout drawings; horizontal rebar splicing of #18 splices were observed in preparation, fabrication and checked after firing to conform to requirements. Tensile Testing of veritical #18 splices were observed in the site testing laboratory for qualification of operations.
- e. Batch Plant Operation - accuracy of material control and temperature control; inspection, generation and control of batch plant print-out records and truck tickets; inspection of materials and batching by qualified QC inspection personnel.
No items of noncompliance, other than that identified in Para-graph 5, were identified.
- 7. Observation of Installation-Compaction and Testing of Structural Fill Around Engineered Safety Features Compartments The inspector observed installation and testing of Class I fill at the west and south sides of the ESFC from about evelation -11' to -
8', and removal / replacement of reject fill at the 48" diameter sumps south of ESFC. These activities were inspected for conformance to the following:
l
8 l
Forked River r!uclear Station, Unit 1, PSAR Appendix SD B&R Specification 2700-206, Rev. 6, " Substructure" M-K Construction Procedure CP-01-FR, Rev. 3, " Placement and Comp 3ction of Class I Backfill" GPU Procedure FR-1-10-04, Rev. O', " Site QA/QC Surveillance Procedure" Performance of the following activities was observed:
- a. Backfill release form was signed by construction manager.
- b. Placement of approved fill in 8" (loose) layers rolled four passes with approved 25 ton vibro-roller over each lift after application of water to each layer (prev'.ous tests established no maximum limit on moisture).
- c. In-situ density tests, using a calibrated instrument (Washing-ton 1/10 cubic foot densometer), conducted by a qualified US Testing Company technician under surveillance of S&W QC engi-neer, tests #127 - 130, fullfilling requirements of ASTM 0 2167-72.
- d. Frequency of in-place density testing exceeded minimum re-quirements of one in-situ test for every full shift of com-paction operation, or one test for each foot thickness of compacted backfill over an area of 18,000 square feet.
- e. Laboratory determination of natural dry density, maximum and minimum densities on soil obtained for each sample identified above, and computation of relative density of cohesion less soils, as required using ASTM D 2049-74,
- f. Relative density results fullfilled requirements that average of all tests have minimum value of 90% and none fall below 75%.
No items of noncompliance were identified.
9
- 8. Review of Ground Water and Slope Stability Records for Maintenance of Dewatering and Safety of Excavation Slopes The Moretrench American Corporation (MTA) has contract for installa-tion and maintenance of the dewatering system surrounding and within the excavation for the Forked River Unit 1 facility. This is not a safety related activity and, therefore is not required to conform to 10 CFR 50, Appendix B. However, maintenance of the required level of ground water within the slurry trench cut-off wall to permit construction in the dry is controlled by MTA in accordance with dewatering requirements established by B&R. MTA personnel provide assurance in control of dewatering by daily water level, pressure and flow readings as well as installation and maintenance of additional equipment as needed to assure safety of the excavation.
Additional procedural requirements of the AE are imposed on the construction r aanger (S&W) for monitoring dewatering of the upper __
unconfined aquifer and the lower confined aquifer to ensure that construction proceeds within safe limits relative to consideration of ground water pressure and stability of excavation slopes.
Construction manager personnel, independent of MTA, daily obtain readings on piezometers, observation wells, inclinometers and em-bankment slope stakes. These are submitted daily to B&R site geotechnical engineer for compilation, analyses and weekly summari-zation. The inspector reviewed these records for period August 4 to September 15, 1978. The records indicate conformance to criteria -
identified in B&R Procedure W0 3700 for Monitoring Instrumentation to Control Dewatering and Excavation.
No items of noncompliance were identified.
- 9. Exit Interview At the conclusion of the inspection on September 15, 1978, a meeting was held at the Forked River site with representatives of the licensee and contractor organization. The inspector summarized the results of the inspection as described in the report.
._ ._ _.-