Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5)ML20134H627 |
Person / Time |
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Site: |
Monticello, Dresden, Browns Ferry, Indian Point, Saint Lucie, Grand Gulf, Byron, Summer, Brunswick, Diablo Canyon, Callaway, South Texas, FitzPatrick, LaSalle ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
02/10/1997 |
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From: |
Racquel Powell NRC OFFICE OF ADMINISTRATION (ADM) |
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To: |
Binder N AFFILIATION NOT ASSIGNED |
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Shared Package |
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ML20134B508 |
List: |
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References |
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FOIA-96-485 NUDOCS 9702110389 |
Download: ML20134H627 (6) |
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Similar Documents at Monticello, Dresden, Browns Ferry, Indian Point, Saint Lucie, Grand Gulf, Byron, Summer, Brunswick, Diablo Canyon, Callaway, South Texas, FitzPatrick, LaSalle |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested ML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217M1851999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required BSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217J3141999-10-15015 October 1999 Requests Emergency Publication of Document Entitled South Carolina Electric & Gas Co;Vc Summer Nuclear Station,Environ Assessment Transmitted on 991015 to Ofc of Fr for Publication ML20217J3281999-10-15015 October 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re Application for Exemption from Requiremets of 10CFR50,Section 50.60(a) for VC Summer Nuclear Station ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217F8851999-10-0808 October 1999 Forwards Insp Rept 50-395/99-06 on 990801-0911.One Violation Occurred Being Treated as NCV ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in 1999-10-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased ML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217M1851999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217J3281999-10-15015 October 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re Application for Exemption from Requiremets of 10CFR50,Section 50.60(a) for VC Summer Nuclear Station ML20217J3141999-10-15015 October 1999 Requests Emergency Publication of Document Entitled South Carolina Electric & Gas Co;Vc Summer Nuclear Station,Environ Assessment Transmitted on 991015 to Ofc of Fr for Publication ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217F8851999-10-0808 October 1999 Forwards Insp Rept 50-395/99-06 on 990801-0911.One Violation Occurred Being Treated as NCV ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient 1999-09-30
[Table view] |
Text
us. Ucs%6LwaW WUMJUEA I URV L,UfAMIMlUiM NRC FOIA REQUEST NUMBER (S)
,,, C, FOIA 485
\ RESPONSE TO FREEDOM OF INFORMATION ACT (FOIA) REQUEST o^1E l FINAL RESPONSE TYPE IX l PARTIAL (5th) l
...../ P B 1 0 1997 ;
DOCKET NUMBER (St (/f app / cable /
i10VESTE R Neil S. Binder l
PART l.-AGENCY RECORDS RELEASED OR NOT LOCATED (See checked boAes/ j No agency records subject to the request have been located. i No additional agency records subject to the request have been located.
Requested records are available through another public distribution program. See Comments section, Agency records subject to the request that are identified in Appendix {es) are already available for public inspection and copying at the NRC Public Document Room,2120 L Street, N.W., Washington, DC.
Agency records subject to the request that are identified in Appendix (es) I are being made available for public inspection and copying y ct the NRC Public Document Room,21201. Street, N.W., Washington, DC, in a folder under this FOI A number, The nonproprietary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staff is now being made available i for public inspection and copying at the N RC Public Document Room,2120 L Street, N.W., Washing *on, DC, in a folder under this FOIA number, Agency records subject to the request that are identified in Appendix (es) may be inspected and copied at the NRC Local Public Document Rcom identified in the Comments section.
Enclosed is information on how you may obtam access to and the charges for copymg records located at the NRC Public Document Room,2120 L Street, !
N.W., Washington, DC.
1 X Agency records subject to the request are enclosed.
- Records subject to the request have been referred to another Federal agencybes) for review and direct response to you.
Fees You will be billed by the NRC for fees totaling $
I You will receive a refund from the NRC m the amount of $ !
In view of N RC's response to this request, no further action is being taken on appeal letter dated , No.
PART ll. A-INFORMATION 'WTHHELD FROM PUBLIC DISCLOSURE l Ctrtain information in the requested records is being withheld from public disclosure pursuant to the exemptions described in and for the reasons stated j in Part it, B, C, and D. Any released portions of the documents for which only part of the record is being withheld are being made available for public j X inspection and copying in the NRC Public Document Room 2:20 L Street. N.W., Washington, DC in a folder under this FOIA number. '
COMME NTS
- Copies of the records identified on Appendix I and the releasable portions of the record identified on Appendix J are enclosed.
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1 eoin muusextsi para 1, RESPONSE TO FREEDOM OF lNFORMATION ACT (FOlA) REQUEST FOIA 96-485 p g 3 0 1997 l
(CONTINUATION) l PART 11.8- APPUCABLE EXEMPTIONS Records subject to the request that are described in the enclosed Appendix (es) U'K are being withheld in their entirety or in part under the l Exems, tion No.(s) and for the reason (s) given below pursuant to 5 U.S.C. 552(b) and 10 CF R 9.17(a) of N RC regulations. ,
i
- 1. The withheld mformaten is properly classified persuant to Executive Order. (Exemption 1)
- 2. The withheld mformation relates solety to the intemal personnel rules and procedures of NRC. (Exemption 2) l l3. The withheld mformaten is specifically exempted from public disclosure by statute mdecated. (Exemption 3) j 4
Sections 141145 of the Atomic Energy Act, which prohibits the discloture of Restricted Data or Formerly Restricted Data (42 U.S.C. 21612165).
I Section 147 of the Atomic Energy Act, which prohibits the disclosure of Unclassified Safeguards information (42 U.S.C. 2167).
- 4. The withheld enformation es a trade secret or commercial or fmancial mformation that is bemg withheld for the reason (s) indicated. (Exemption 4) 4 The mforerstion is considered to be confidential busmess (propnetary) mformation The mformation is considered to be proonetary mformation pursuant to 10 CFR 2 790ldpl16 The mformation was submitted and received m confidence pursuant to 10 CFR 2 790(d)(2)
- 5. The withheld mformation consists of mteragency or mtraagency records that are not available through discovery dunng litigaten (Exemption 6). Applicable Privilege:
lDehberative Process Disclosure of predecisional mformation would tend to mhibit the open and frank exchange of ideas essential to the dehberative process X lWhere portionsrecords becauseare withheld of m thetheir f actsentirety. the facts are mentncably enouiry intoentertwined withprocess the predecisionalinformation There also are no reasonably seare the release would permet en indirect the predecisional of the agency l
~ ' ~
Attomey work product pnvilege IDocuments prepared by an attornev m contemplation of htigation i Attorney client privilege. (Confidential communications between an attorney and his/her client.)
- 6. The withheld mformation es enempted from public disclosure because its disclosure would result in a clearly unmarranted mvasion of personal pnvacy (Exemption 6)
- 7. The withheld mformation consists of records compiled for law enforcement purposes and es bemg withheld for the reasontsi mdicated (Exemption 7)
Disclosure could reasonably be expected to mtcrfere with an enforcement proceedmg because it could reveal the scope, direction, and focus of ,
enforcement efforts, and thus could possibly allow recipients to take action to shield potential wrongdomg or a violaten of N RC requirements i from investigators. (Exemption 7 (A)) j Disclosure would constitute an unwarranted invasen of personal privacy. (Exemption 7(C)) l v The mformation consmis of names of indmduals and other m'ormation the disclobute c,f which could reasonat ly be emDetted to reveal identities of E confidential sources. (Exemption 7 (D))
l lIOTHER !
l PART 11. C-DENYING OFFICIALS i Pursuant to 10 CFR 9 25tb) ed or 9 25(ci of the U S. Nuciear Regu<atory Comm.ssion regulations, it has been determined that the information withheld is exempt from pro-duction or disclosure, and that n. producten or dmclosure is contrary to the public interest. The persons responsible for the denial are those officiais identif 4ed below as denyin0 o*f cials and the Director, D,ves on of Freedom of Ir* format on and Pubhcatens Services. Of fice of Admin.stration. for any den als that may be appealed to the E necutive Director for Operations (EDO)
DENYlNG OFFICIAL l TIT LE / OFFICE RECORDS DENIED APPELLATE OFFICIAL l
Director Office of Nuclear * " "'"
- IFrankJ.Miraglia s Reactor Regulatinn App J. K X l
l I
I l PART 11. D- APPEAL RIGHTS The d2nist by each denying official identified m Part 11 O may be appealed to the Appellate Official identified there. Any such appeal must be made in wnting within 30 days of receipt of this response. Appeals must be addressed, as appe, anate, to the Executive Director for Operatens to the Secretary of the Commission, or to the inspector General, U S. Nuclear Argulatory Commission. Washmgto% DC 206, and should clearly state on the envelope and in the letter that it is an "Appeat from an initial FOI A Decision.
NRC FORM 464 (Part 2) (191) U S. NUCLEAR REGULATORY COMMISSION
Q Re: FOIA-96-485 APPENDIX I .
RECORDS BEING RELEASED IN THEIR ENTIRETY t
NO. DATE DESCRIPTION /(PAGE COUNT) 4
- 1. Various Investigation Status Records,
Subject:
dates Alleged Discrimination of I&C Technician for Reporting Safety Concerns - 3 pp
- 2. Undated E-mail, from James Dockery to LJW2,
Subject:
DOL Case Reply - 1 p
- 3. 03/03/95 Exhibit 1 to ROI 2-95-008, Investigati on Status Record - 1 p
- 4. 03/09/95 Memorandum to Bruno Uryc from William J.
McNulty,
Subject:
Notification of Initiation of Investigation: St. Lucie Nuclear Plant:
, Alleged Discrimination of I&C Technician for Reporting Safety Concerns (Case No. 2 008/RII-95-A-0026) -1p
- 5. 03/13/95 E-mail from JJD to LMS,
Subject:
Allegation
- RII-95-A-0026 - 1p
- 6. 03/17/95 E-mail from JJD to OXD,
Subject:
RII-95-A- ,
0026 (OI Ref No.: 2-95-008) -1p '
- 7. 06//07/95 E-mail from JDD to OXD,
Subject:
RII-95-A-0026 (2-95-008) -1p
- 8. 08/23/95 E-mail from JDD to LMS,
Subject:
EICS Files -
1p
- 9. 09/25/95 Memorandum to: Carolyn F. Evans from William J. McNulty,
Subject:
St. Lucie Nuclear Plant: Alleged Discrimination Against an I&C Technician for Reporting Safety Concers (Case No. 2-95-008 - 1p
- 10. 10/30/95 E-mail from JDD to BXU,
Subject:
RII-95-A-0026 - 1p
- 11. 02/20/96 E-mail from James Dockery to SKD,
Subject:
Request for Court Reporter Services with attachment - 2 pp
2
- 12. 03/04/96 E-mail from James Dockery to SKD,
Subject:
Request for Court Reporter, with attachment -
2 pp
- 13. 04/02/96 E-mail from James Dockery to CFE,
Subject:
2-95-008 - Alleger Interview - 1p
- 14. 05/30/96 E-mail from James Dockery to CFE, Subject OI Case 2-95-008 - 1p
- 15. 05/30/96 E. Mail from James Dockery to EXL2,
Subject:
St. Lucie (OI Investigation 2-95-008) - 1p
- 16. 07/31/96 OI Report of Investigation, St. Lucie Nuclear Plant: Alleged Discrimination Against an Instrumentation and Control Technician for Reporting Safety Concerns - 13 pp
- 17. 08/05/96 Memorandun to S. D. Ebneter from W. J.
McNulty,
Subject:
St. Lucie Nuclear Plant:
Alleged discrimination Against Instrumentation and Control Technician for Reporting Safety Concerns (Case No. 2 008/RII-95-A-0026) - 1p
- 18. 08/22/96 Memorandum to File: Case No. 2-95-008, from James D. Dockery, Sr.,
Subject:
Telephone Conversation with Alleger - 1 p
- .. . _- -_= _ __ ._ .
Re: F01A-96 485 APPENDIX J RECORDS BEING WITHHELD IN PART NO. DAT_E DESCRIPTION /(PAGE COUNT)/ EXEMPTIONS
- 1. 4/13/94 Memorandum for William Russell from Ashok Thadani
Subject:
Results of (SMM) Screening Meetings (2 pages)
EX. 5 l
I l
1 I
1 I
- J Re: F01A 96 485 APPENDIX K RECORDS BEING WITHHELD IN THEIR ENTIRETY NO. DAIE DESCRIPTION /(PAGE COUNT)/ EXEMPTIONS i 1. 11/18/94 Memorandum to Patrick Baranowsky et al. . from Alfred Chaffee.
Subject:
Request for Review of Draft Technical
! Evaluation Report attaching Draft Technical Evaluation l Report. Engineering Analysis and Incremental Core Damage Frequency Estimation for Four Unreported Potentially i Risk Significant Events (UPRSE) ad One Reported Event (170 pages) EX. 5 l
i j
j
T DESEVOISE & PLIMPTON !
875 THIRD AVENUE 55513TH STREET N w 21 AVENUE GEORGE V 1 CREED COURT. S LUDGATE MILL WASHINGTON. DC 20004 75006 PARIS NEW YORK, NY 10022 TELtmONE (2o2) 383.e00o TEu PHONE os.1)4o 731212 LONDON EC4M 7AA TEuPHONE M 171) 329 0779 (p} 2) g TELECOPIER (202) 383-8118 TELI_ COPIER (331) 47 20 JO 82 TELECOPIER (44-171) 329 0860 13/F ENTERTAINMENT BUILDING 30 QUEEN'S ROAD CENTRAL 1065 BUDAPEST HONG KONG RtVAY KOZ 2 ati2 TELECoPIER: (212) 909-6836 TELEPHONE (852) 2810 7918 TELEPHONE (36-1) 1310845 T ELECOPIER (852) 2810 9828 TELECOPtER (361) 132 7995 November 14, 1996 Russell Powell
'
- NEI Chief of the FOIA/LPDR c. a hu . ff -/ -/8{
Nuclear Regulatory Commission ;;g ;p 3 , g f p_. 9 {,,,
Mail Stop T6D8
^~- -
Washington, D.C. 20555-0001 Ref?M CrM5 ., . . _ , ,
Dear Mr. Powell:
This is a request under the Freedom of Information Act, 5 U.S.C. S 552. I request that a copy of all records and other documents that fit the following description be sent to me:
- 1) All records or other documents from January 1, 1 1993 to the present that are not currently in the !
public documents room and that relate to Florida Power and Light's St. Lucie Nuclear Power Plant (Unit 1 and/or Unit 2).
- 2) The number of inspection hours (by quarter) devoted by the NRC to all licensed nuclear plants in region 2 since January 1, 1993.
In order to help determine my status for the purpose of assessing any fees, you should be advised that I represent a company, and I am seeking information for use related to the company's business.
Please advise me of any fees associated with processing this request.
Sincerely,
- , ~
Neil S. Binder 20280632 01 Q ' 7n . ')
W/4/&Yf
. - - - - . . - . . . . - . . . . . - - . - . . - . - . . - = - - - - - - . - . -
LIMITED }ISTRIBUTION -- NOT FOR PUBLIC DMCLOSURE
,. INVESTIGATION STATUS RECORD (naae 3) i Case No.: 2-95-008 Facility: ST. LUCIE NUCLEAR PLANT Case Agent: DOCKERY Priority: HIGH (L. REYES, DEP RA)
Subject / Allegation: ALLEGED DISCRIMINATION OF I&C TECHNICIAN FOR REPORTING SAFETY CONCERNS l Monthly Status Report:
l 06/30/96: Status: RID ECD: 07/96 !
l 07/31/96: Priority changed to High at 07/09/96 meeting with EICS and Deputy RA.
Closed / Unsubstantiated 08/05/96: Issued i
i i
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Closed: 07/31/96 Issued: 08/05/96 Action: U , l
t I LIMITED DISTRIBUTION--NOT FOR PUBLIC DISCLOSURE W/0 01 APPROVAL
LIMITED}ISTRIBUTION--NOTFORPUBLICD" CLOSURE 1 , INVESTIGATION STATUS RECORD l
4 Case No.: 2-95-008 Facility: ST. LUCIE NUCLEAR PLANT Allegation No.: RII-95-A-0026 Case Agent: DOCKERY Docket Nos.: 050-335; 050-389 Date Opened: 03/03/95
]
Source of Allegation: ALLEGER Priority: HIGH (L. REYES, DEP RA)
Notified by: EICS Staff
Contact:
Category: IH Case Code: RP Subject / Allegation: ALLEGED DISCRIMINATION OF I&C TECHNICIAN FOR REPORTING SAFETY l 4
CONCERNS Monthly Status Report: page 2 10/31/95: On 10/06/95, the NRC RII Regional Administrator forwarded a letter to the licensee, Florida Power and Light Co. (FP&L) directing FP&L to provide the NRC with the basis for the employment i,ction against the alleger, i
. Gary L. PHIPPS, and action planned by the ?icensee to assure that the
, employment action against the alleger does not have a chilling effect on
- other employees. 01 has requested to be timely advised when the licensee's response is obtained so that a response may be utilized in the formal 01 interview of the alleger. Status: PEN ECD: unscheduled j 11/30/95: FP&L requested and was granted an extension in filing its response to the NRC " Chilling Effect" letter sent to the licensee on 10/06/95. The FP&L
, response is anticipated during December 1995. Status: PEN
. ECD: unscheduled 12/31/95: No change status. Status: PEN ECD: unscheduled 01/31/96: On 01/10/96, 0I received a copy of the licensee response to the NRC
_ " Chilling Effect" letter with an attached licensee investigation of the
, alleger's concerns. On 10/30/95 the alleger and the licensee entered 4
into an agreement to settle the alleger's D0L complaint. Neither party
] to the settlement admitted to any culpability. On 11/30/95 a D0L Administrative Law Judge issued a Recommended Order of Dismissal of the alleger's complaint based on the settlement agreement. The Secretary of 1
Labor has not yet issued a final ruling on the matter. Status: PEN
- ECD
- unscheduled 02/29/96: 01 interview of the alleger, PHIPPS, scheduled for 02/27/96 had to be rescheduled due to commercial carrier problems. Status: FWP ECD: 08/96 03/31/96: Based upon the assignment of Special Agent Dockery to the Region I
- Millstone Nuclear Plant investigation (Case No. 1-96-010) on a full time basis, the case status has changed to "Pending." Status: PEN i ECD: unscheduled 04/30/96: No change. Status: PEN ECD: unscheduled a
05/31/96: No change. Status: PEN ECD: unschMuled
, LIMITED DISTRIBUTION--NOT FOR PUBLIC DISCLOSURE W/0 01 APPROVAL '/ 2 (
4 LIMITED %STRIBUTION--NOTFORPUBLICDNLOSURE INVESTIGATION STATUS RECORD Case No.: 2-95-008 Facility: ST. LUCIE NUCLEAR PLANT Allegation No.: RII-95-A-0026 Case Agent: DOCKERY Docket Nos.: 050-335; 050-389 Date Opened: 03/03/95 Source of Allegation: ALLEGER Priority: NORMAL Notified by: EICS Set by: S. EBNETER, RA Category: IH Case Code: RP Subject / Allegation: ALLEGED DISCRIMINATION OF I&C TECHNICIAN FOR REPORTING SAFETY CONCERNS Remarks:
Monthly Status Report:
03/03/95: The alleger, Gary PHIPPS, a Digital Instrumentation and Control (I&C) technician at St. Lucie, stated that his Florida Power and Light Company management discriminated against him for raising concerns regarding system configuration and maintenance, and for reporting safety concerns to SPEAK 0VT (the site employee concerns program). PHIPPS stated that the adverse action was in the form of his being the only I&C technician that was not assigned any outage work. Status: FWP ECD: 07/95 03/31/95: The alleger was telephonically contacted by OI on March 16, 1995. The alleger advised that he was in the process of documenting his concerns for both the NRC and his anticipated D0L complaint. The alleger agreed to be interviewed by 01 af ter he has completed documenting his allegation which he will forward to the RII allegation coordinator. 01 has advised the regional allegation coordinator to expect the alleger's complaint in the near future and requested that 01 be notified upon receipt. RA has set priority at normal on 03/27/95. Status: FWP ECD: 09/95 04/30/95: The alleger was contacted on 04/13 and advised that he was delayed in preparing documentation of allegations promised during 01 telephone interview on 03/16. Further interview of alleger delayed pending notification of receipt of alleger's documentation by RII allegation coordinator and review by 01. Status: FWP ECD: 09/95 05/31/95: Awaiting notification from RII EICS of receipt of alleger's supporting documentation. Status: FWP ECD: 09/95 06/30/95: On June 28 EICS:RII provided 01 with a copy of the alleger's April 11, 1995, letter to RII and the 00L detailing the alleger's discrimination complaint against the Florida Power and Light Company. This documentation was requested by 01 from the alleger during March 1995.
Status: FWP ECD: 09/95 07/31/95: No investigative resources available. Status: NRA ECD: unscheduled 08/31/95: No change in status. Status: NRA ECD: unscheduled 09/30/95: No change in status. Status: NRA ECD: unscheduled
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LIMITED DISTRIBUTION--NOT FOR PUBLIC DISCLOSURE W/0 01 APPROVAL
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