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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 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 Pass Dates ML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L0061999-10-0101 October 1999 Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212K8771999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Three Mile Island on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Provides Historical Listing of Plant Issues & Insp Schedule ML20212K8551999-09-30030 September 1999 Informs That During 990921 Telcon Between P Bissett & F Kacinko,Arrangements Were Made for Administration of Licensing Exams at Facility During Wk of 000214.Outlines Should Be Provided to NRC by 991122 ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld ML20211A4261999-08-19019 August 1999 Forwards Insp Rept 50-289/99-04 on 990606-0717.Two Severity Level 4 Violations Occurred & Being Treated as Noncited Violations ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210N7601999-08-10010 August 1999 Informs That NRC Staff Reviewed Applications Dtd 990629, Which Requested Review & Approval to Allow Authority to Possess Radioactive Matl Without Unit Distinction Between Units 1 & 2.Forwards RAI Re License Amend Request 285 ML20210N7191999-08-0606 August 1999 Forwards Notice of Partial Denial of Amend to FOL & Opportunity for Hearing Re Proposed Change to TS 3.1.12.3 to Add LCO That Would Allow Continued HPI Operation ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210B8231999-07-21021 July 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20209H9401999-07-15015 July 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed ML20209G2451999-07-15015 July 1999 Advises That Suppl Info in Support of Proposed License Transfer & Conforming Adminstrative License Amends,Submitted in & Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident ML20216D9861999-07-12012 July 1999 Forwards RAI Re 981019 Application Request for Review & Approval of Operability & SRs for Remote Shutdown Sys. Response Requested within 30 Days of Receipt of Ltr ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209D8451999-07-0808 July 1999 Forwards Insp Rept 50-289/99-06 on 990608-11.No Violations Noted.Overall Performance of ERO Very Good & Demonstrated, with Reasonable Assurance,That Onsite Emergency Plans Adequate & That Util Capable of Implementing Plan ML20209D6291999-07-0808 July 1999 Forwards Notice of Withdrawal & Corrected TS Pages 3-21 & 4-9 for Amend 211 & 4-5a,4-38 & 6-3 for Amend 212,which Was Issued in Error.Amends Failed to Reflect Previously Changes Granted by Amends 203 & 204 ML20209D5141999-07-0808 July 1999 Forwards RAI Re 981019 Application & Suppl ,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License ML20196J5631999-07-0101 July 1999 Informs That Util 981203 Joint Application with Amergen Energy Co Marked Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License ML20196J7701999-06-29029 June 1999 Forwards LAR 285 for License DPR-50,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20196J7651999-06-29029 June 1999 Provides Updated Info Re Loss of Feedwater & Loss of Electric Power Accident Analyses to Support TS Change Request 279 Re Core Protection Safety Limit,As Discussed at 990616 Meeting ML20209C0391999-06-29029 June 1999 Forwards LAR 77 to License DPR-73,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-2 License to Amergen,Radioactive Matl May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20196G2061999-06-23023 June 1999 Requests That NRC Update Current Service Lists to Reflect Listed Personnel Changes That Occurred at TMI 05000289/LER-1999-006, Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements1999-06-23023 June 1999 Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements ML20196D2171999-06-17017 June 1999 Forwards Pmpr 99-9, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508- 0604.New Summary Personnel Table Was Added to Rept Period.Matl Scientist Joined Staff Period ML20196A0431999-06-15015 June 1999 Providess Notification That Design Verification Activities Related to Calculations Supporting Analytical Values Identified in Gpu Nuclear Ltr to NRC Has Been Completed 05000289/LER-1999-004, Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT1999-06-0909 June 1999 Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT ML20212K2671999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20212K2541999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20195E3281999-06-0404 June 1999 Forwards Application for Amend to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20195E2751999-06-0404 June 1999 Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1 ML20195C5721999-06-0202 June 1999 Forwards Description of Gpu Nuclear Plans for Corrective Actions for 1 H Fire Barriers in Fire Zones AB-FZ-3,AB-FZ-5, AB-FZ-7,FH-FZ-2 & Previous Commitments for Fire Zones CB-FA-1 & FH-FZ-6 ML20207E2561999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Change in ECCS Analyses at TMI-1 ML20195B2461999-05-21021 May 1999 Forwards Itemized Response to NRC 990506 RAI for TS Change Request 279 Re Core Protection Safety Limit ML20206R6461999-05-13013 May 1999 Forwards Rev 39 of Modified Amended Physical Security Plan for TMI ML20206K6301999-05-0707 May 1999 Provides Addl Info Re TMI-1 LOFW Accident re-analysis Assumptions for 20% Average SG Tube Plugging as Discussed on 990421 05000289/LER-1999-003, Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC1999-05-0707 May 1999 Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC ML20206H0781999-04-30030 April 1999 Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl ML20206J4811999-04-30030 April 1999 Provides Summary of Activities at TMI-2 During First Quarter of 1999.TMI-2 RB Was Not Inspected During Quarter.Routine Radiological Surveys of Auxiliary & Fuel Handling Bldgs Did Not Identify Any Significant Adverse Trends ML20206E4121999-04-27027 April 1999 Requests That TS Change Request 257 Be Withdrawn ML20206C5211999-04-23023 April 1999 Requests Mod to Encl Indemnity Agreement Number B-64,on Behalf of Gpu & Affiliates,Meed,Jcpl,Penelec & Amergen Energy Co,Llc.Ltr Supersedes & Withdraws 990405 Request Submitted to NRC ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 1999-09-09
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20055F5681990-07-11011 July 1990 Forwards TMI Citizens Monitoring Network Rept for June 1990. No Unusual Events Reported.Stations 9,10 & 11 Added to Network & Three Addl Monitors to Go on-line for Jul ML19325E9801989-11-0101 November 1989 Requests That Author Name Be Placed on Distribution List Re Schedule of Hearing in Alchemie Case.W/Certificate of Svc. Served on 891101 ML20246P4131989-07-0707 July 1989 Presentation of Argument.* Informs That Author Will Present Argument on Behalf of Susquehanna Valley Alliance & TMI Alert on 890726 Re Appeal of Initial Decision LBP-89-7.Svc List Encl ML20247F8061989-07-0505 July 1989 FOIA Request for Documentation Re Incidents of Drug &/Or Alcohol Abuse During Past Five Yrs Amoung Employees or Contractors ML20247E6951989-06-27027 June 1989 Advises That Newly Formed Environ Conservation Organization Intends to Oppose Any Util Actions That Might Impact Negatively on Future Operability of Facility ML20247H3631989-06-26026 June 1989 Advises of Formation of Resources Conservation Organization. New Group Intends to Oppose Any Util Actions That Might Impact Negatively on Future Facility Operability.Ad Rossin Will Serve as Organization Coordinator ML20245E9551989-06-17017 June 1989 FOIA Request for TMI-2 Accident Rept ML20245G2091989-05-23023 May 1989 Requests Commission to Require Continuation of Existing real-time & Other Monitoring in Vicinity of TMI Reactors in Commonwealth of Pa.Status Rept of Current & Proposed Monitoring in TMI Area by Entities Including Util Requested ML20245B3981989-05-0808 May 1989 Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant ML20244C1211989-04-11011 April 1989 Forwards Susquehanna Valley Alliance/Tmi Alert Table of Authorities Inadvertently Left Out of Brief in Support of Notification to File Appeal.W/Certificate of Svc ML20244D8721989-03-23023 March 1989 Raises Concerns Re Unexplained Actuation of Warning Siren at Plant,Located Less than 1 Mile from Author Residence ML20245B4081989-03-10010 March 1989 Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant ML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20235N1781989-01-26026 January 1989 FOIA Request for Easter Sunday Dosimetry Rept, Ref in Ha Falk 790426 Memo ML20245B4091989-01-23023 January 1989 Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah ML20245B4101989-01-19019 January 1989 Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl ML20205R4191988-10-31031 October 1988 Requests Time to Make Brief Statement at 881103 Special Hearing on Disposal of Water Generated by 1979 Accident at Plant.Served on 881104 ML20205F7441988-10-24024 October 1988 Requests to Make Oral Statement at Hearing Re Disposal of accident-generated Water at TMI-1.Served on 881024 ML20205R6061988-10-24024 October 1988 Requests Time to Make Statement During Special Hearing Re Issue of Public Health & Safety Concerning Disposal of Water from Tmi.Served on 881103 ML20205F7671988-10-22022 October 1988 Requests Time to Speak at 881103 Hearing in Lancaster,Pa Re Util Plan to Evaporate 2.3 Million Gallons of Radioactive Water Generated by 1979 Accident at Tmi.Served on 881027 ML20206D8951988-10-15015 October 1988 Expresses Opinion That Plants Should Remain Closed Until Converted to Alternative Fuel Source ML20245B4121988-10-14014 October 1988 Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns ML20206D9711988-09-0808 September 1988 Forwards Ltrs Exchanged Between NRC & Author in 1984 Re Problems in Commercial Nuclear Power Field & Change in Federal Regulations to Allow Senior Reactor Operator to Deviate from Tech Specs in Emergency ML20153D0641988-08-24024 August 1988 Requests Hearing Date for Wk of 881114 Instead of 881031 to Suit Author Witnesses ML20206D9451988-08-12012 August 1988 Annotated Ltr Expressing Appreciation for Reply to & Assurance in Response to Concerns Pertaining to Operation of Ref Plants ML20245D6611988-08-0808 August 1988 Submits Listed Comments in Response to Re Safety Practice to Schedule Nuclear Plant Operating & Maint Personnel for 16 H Shifts &/Or Excessive Overtime ML20206E0281988-07-0707 July 1988 Advises That Nuclear Industry Overlooked Most Important Lesson Resulting from TMI Accident,To Wit,That Station Operator/Mgt Official Stationed in Control Room Would Have Prevented Accident ML20150D5991988-07-0707 July 1988 Advises That Piccioni Affidavit Noted in Susquehanna Valley Alliance & TMI Alert 880620 Response to Licensee Motion for Summary Disposition Will Not Be Received Due to Piccioni Schedule Not Permitting Completion of Affidavit ML20150A7961988-06-30030 June 1988 Comments on Util 880616 Request to Suspend Antitrust License Condition.Economic Advantages for Util Owning Nuclear Power Plants Have Failed to Materialize ML20155B6651988-06-16016 June 1988 FOIA Request for plant-specific Documents Re Fire Protection Requirements,Insp repts,hardware-specific Deficiencies & NRC Communications W/Util ML20197F5421988-06-0202 June 1988 FOIA Request for Documents Including 811110 Generic Ltr 81-38 & Nrc/Tmi 83-062 ML20206E0361988-04-29029 April 1988 Opines That 10CFR50.54(x) & (Y) Superfluous & Dangerous.Nrc Should Instruct Operators Not to Depart from Tech Specs in Emergency.Author Resume Detailing Experience in Commercial Nuclear Power Field Encl ML20151P0001988-04-20020 April 1988 Requests Time on Agenda of Next Prehearing Conference Re Disposal of accident-generated Water at TMI-2 So That Author Can Make Oral Statement.Served on 880420 ML20154K2551988-04-0909 April 1988 Requests Info Re Radiological Releases from TMI-2 Accident on 790328 as Recorded by in-plant Monitoring Equipment for First 42 H of Accident.Radioiodine Releases Measured by Iodine Monitoring Sampler Should Also Be Included ML20151D0701988-03-22022 March 1988 Forwards Radiation Monitoring Sys for Nuclear Power Plants (W/Special Ref to TMI Nuclear Power Station) ML20155A7431988-02-24024 February 1988 Discusses Safety Problems at Comm Ed Nuclear Power Plants Re Risking Fuel Meltdown by Turning Off Safety Sys as Directed by Util Policy in Emergency If Core Cooling Is Adequate. Vice President Instruction Encl ML20148G9001988-02-0101 February 1988 FOIA Request for Documents Re 10CFR50,App R Insps & Enforcements ML20206E0431988-01-29029 January 1988 Expresses Concern Re Two Hazardous Practices at Ref Plants, Including Risking Meltdown by Authorizing Operators to Turn Off Nuclear Plant Safety Sys During Emergency ML20195J1161988-01-12012 January 1988 Requests That Author Name Be Placed on List of Individuals Speaking at Prehearing Conference Re Deposition of accident- Generated Water at Plant.Served on 880120 ML20195J0761988-01-0606 January 1988 Requests Permission to Make Comments at Hearing on Disposal of Water at Tmi.Served on 880120 ML20148H7551988-01-0404 January 1988 Opposes Plan to Steam Vent Radioactive Water from Tmi. Local Residents Should Not Have to Suffer Any Further Health Risks as Result of Util Negligence.Served on 880125 ML20234B9891987-12-22022 December 1987 Opposes Release of Any Radioactive Contaminants.Release of Radioactive Vapor Will Continue to Contaminate Area & Further Seepage Not Warranted.Served on 880104 ML20149G1051987-12-18018 December 1987 Opposes NRC Reduction at TMI-2.Reducing Staff Prior to Completion of Core Removal Inappropriate & Misguided Move. Recent Shutdown of Oyster Creek for Incident Re Destruction of Data Decreases Util Standing W/Local Residents ML20237C5831987-12-16016 December 1987 FOIA Request for Documents Re Nuclear Leak at Plant ML20237E7401987-12-0808 December 1987 Requests Opportunity to Comment Before ASLB on Proposed Evaporation of 2.3 Million Gallons of Radioactive Water from Facility.Served on 871217 ML20237E7321987-12-0707 December 1987 Requests to Make Comment on Util Proposed Evaporation of Accident Generated Water at Facility Before Aslb.Served on 871217 ML20236G8491987-10-15015 October 1987 FOIA Request for Ofc of Investigations & Ofc of Inspector & Auditor Repts Re Ucs Request for NRC Investigation Whether Gpu Made Matl False Statements Concerning Environ Qualification of Safety Equipment at Facility ML17303A6161987-09-30030 September 1987 Forwards Scenario Review for Rancho Seco Emergency Preparedness Exercise,871104. Incomplete Scenario Provided for Review.Plant data,in-plant Chemistry & Radiological Data & Controller Info to Support Fire Drill Missing Elements ML20235V1311987-09-24024 September 1987 FOIA Request for Procedures Used to Obtain Sample of Water Known as Accident Generated Water Contained in TMI-2, Including Location from Which Sample Drawn,Number of Samples,Method for Analysis & Analysis of Water ML20235T7341987-09-0101 September 1987 Requests That EIS Documents Re Meltdown Prepared by Impartial Sources Be Made Available to Public.Observation of Plant Life Indicates Level of Contamination of General Environ Causing Widespread Severe Damage 1990-07-11
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L 262 Sheffield Lane !
- Glen Ellyn IL 60137 l 1 (312)790-2288
May 3, 1984 l
i Dr. Nunzio J. Palladino Chairman [
U. S. Nuclear Regulatory Comission
Dear Mr. Chairman:
You are endeavoring to provide assurance that Three Mile Island Unit 1 l
will be operated safely. Before issuir m Operating License, you want to be ,
sure that General Public Utilities Nucle *orporation's executives will ;
operate Three Mile Island Unit 1 to generate electric!ty and not cnaanger i public health and safety.
I You changed Federal Regulations after the Three Mile Island accident. l Now, a senior operator in a commercial nuclear power plant is to deviate from !
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technical specifications in an emergency. In an emergency, a sento* operator >
l is to devise action to protect public health and safety if it is not immedi- t ately apparent that following technical specifications provides protection. [
The nuclear plant operator at Three Mile Island deviated from technical !
specifications at the beginning of the accident. The operator turned off an I emergency signal and shut down the emergency core cooling system. The shift ;
I supervisor, a senior operator, permitted the nuclear plant operator to deviate from technical specifications to shorten plant down time. The shift supervi- :
sor was working to get the nuclear plant back on line as soon as possible. l Before the accident, the station manager and his, supervisors deviated )
from technical specifications and kept the Three File Island nuclear plant on ,
line generating electricity for Metropolitan Edison Corpany. The electro-
- nagnetic relief valve started to leak several months before the accident.
Supervisors kept the block valve open. The relief valve was leaking badly l several days before the accident. Supervisors operated three reactor plant [
l systens abnormally to overcome problems caused by the reactor coolant system l
1eak, f During the first day of the accident, action devised by Three Mile t Island's anagers, supervisors, and operators to cool the nuclear fuel !
deviated from tecanical specificatiora. At least six senior operators devised ;
action to cool the nuclear fuel. None was successful and the nuclear reactor l boiled out of control all day.
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Or. Nunzio J. Palladino May 3, 1984 Page Two Reactor coolant system pressure was below the setpoint of the emergency core cooling system most of the morning and all afternoon. Technical speci-fic.ations required emergency pe'nps to pump water into the reactor and coolant pumps to circulate coolant through the reactor core.
Late in the afternoon, a Babcock and Wilcox manager recomended ti tt emergency core cooling pumps pump fou, to five hundred gallons of water )er minute into the nuclear reactor. The General Public Utilities vice-pres dent for generation discussed the situattor, with the Metropolitan Edison vice-president for generation. The two executives decided that water should be pumped into the nuclear reactor. Metropolitan Edison's vice-president gave the order to the station manacer. ~
Operators shut the block valve for the electromagnetic relief valve and started pumping water into the nuclear reactor at five twenty-three p.m. As rtactor coolant system pressure increased, the station manager, in consulta-tion with Babcock and Wilcox engineers, made plans to start a reactor coolant pump. At seven-fifty p.m. , reactor coolant pump 1A was started. ,
At eight p.m., reactor coolant pump 1A was pumping water through the '
nuclear reactor and a steam generator to remove decay heat from the nuclear fuel. The steam generator was steaming to the main condenser. Cool down of Three Mile Island's nuclear reactor had commenced. Operators were operating the Three Mile Island nuclear plant to remove decay heat from the reactor and '
cool the nuclear core as engineers had designed the plant to be operated.
Engineers design commercial nuclear power plants to keep fuel rods intact and prevent release of radioactive material to protect public health and safety. Technical specifications are rules for operating a comercial nuclear l
i 4 power plant developed from the plant design. Technical specifications are rules for operators to follow during normal operitions and emergencies to operate the nuclear plant as designed.
Operators following a commercial nuclear power plant's technical speci-fications confine radioactive fission products within the fuel rods of the reactor core and prevent the release of radioactive material. Operators !
operating a comercial nuclear power plant in accordance with technical specifications during normal operations and emergencies protect public health i and safety. l j 1 urge you and your colleagues to cancel the federal Regulation wh;ch i permits a licensee to depart from technical specifications when operating a nuclear plant in en emergency. I urge you to tell the president of General i
Public Utilities Nuclear Corporation that you expect him to promulgate policy i liial Ti..cc M;1e Is16ad Unit 1 is to te operated in accoruance with the Operat-ing License and Technical Specifications.
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Dr. Nunzio J. Palladino May 3, 1984 Page Three l
I urge you and your colleagues to have Nuclear Regulatory Comission inspectors inspect Three Mile Island Unit 1 to verify that the president of General Public Utilities Nuclear Corporation has implemented policy that operators are O operate Three Mile Island Unit 1 in accordance with the Oparating License and Technical Specifications. I urge you to instruct the Nuclear Regulatory (. omission staff to have an inspector inspect Three Mile Island Unit I daily. Have the Nuclear Regulatory Comission inspect daily to verify that Three Mile Island Unit 1 is being operated in accordance with the Operating License and Technical Specifications. Have an inspector inspect daily ann report resalts to the Regionc1 Administrator.
Since:ely yours, Charles Young Copy to:
John F. Ahearne, Ccmissioner U.S. Nuclear Regulatory Corraission Washington, D.C. 20555 Thomas M. Roberts, Comissioner U.S. Nuclear Regulatory Cornission Washington, D.C. 20555 Victor Gilinsky, Comissioner U.S. Nuclear Regulatory Comission Washington, D.C. 20556 James K. Asselstine, Cornissioner U.S. Nuclear Regulatory Comission Washington, D.C. 20555
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262 Sheffield Lane Glen Ellyn, IL 60137 (312)790-2288 June 14, 1984 Dr. Nunzio J. Palladino Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Chairman:
When Three Mile Island's Unit 2 nuclear plant operator turned off the ,
emergency safeguards signal and shut down the emergency core cooling system at the beginning of the accident, he lost the safety functions of two reactor plant safety systems. Abundant cooling water to transfer heat from the reactor core was not provided because the operator shut down the amergency pumps. The protection system sensed the accident condition but could no longer initiate the emergency core cooling system because the operator turned off the initiating signal.
After the safety systen sa'ety functiers were lost, reactor coolant system pressure contir.ued to decrease and reactor coolant temperature in-creased. Safety limits were e>ceeded and fuel cladding fractured. Exceeding safety limits breected a physical barrier designed to guard agairst the uncontrolled release of radioactivity and protect public healt.' and sa'ety against the hazards of nuclear radiation.
When the Three Mile Island's nuclear plant operator departed from techni-cal specifications by turning off the emergency shfeguards signal and shutting the emergency core cooling system, he created a substantial safety hazard, a "loss of safety function to the extent that there is a major reduction in the i degree of protection provided public health and safety."
"Substantial safety hazard" is defined in the Code of Federal Regu-lations, 10 CFR 21.3 (k). Protection system safety functions are outlined in Criterion 20; energency core ccoling safety functions in Criterion 35.
Criterion 20 and Criterion 35 are two of the "General Design Criteria for Nuclear Power Plants," Appendix A to 10 CFR 50. Safety limits for nuclear reactors are defined in 10 CFR 50.36 (c)(1). Reactor core safety limits for Three Mile Island's nuclear reactor are defined in paragraph 2.1, "Three Mile Island Nuclear Station Unit 2 Technical Specifications."
An operator created a substantial safety hazard at Conconwealth Edison Company's Zion Unit I nuclear plant the morning of February 2,1979. With the reactor at 25! power, an operating engineer, a licensed senior operator, deviated f rom technical specifications and turned off the safety injection system. An abnormal plant condition had given a start signal to the safety injection system. A second signal would start the safety injection system and shut down the reactor. The operating engineer told me he turned off the safety injection signal because he thought he had the reactor plant under control and he wanted to keep the plant on line generating electricity for Co.nonwealth Edison.
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' Dr.. Nunzio J. Palladino Page 2 i 0
Three times in the past I infomed authorities that authorizing a senior operator to deviate from technical specifications when operating a commercial nuclear power plant creates a substantial safety hazard. I infomed author-ities as required by the Ccde of Federal Regulations,10 CFR 21.
I informed Mr. James J. O'Connor, President of Commonwealth Edison Company, Chicago, Illinois, that Comonwealth Edison Company creates a sub-stantial safety hazard operating the company's nuclear power plants: 1 informed Mr. O'Connor that Comenwealth Edison creates a substantial safety hazard by company policy which permits a senior operator operating a nuclear plant to deviate from technical specifications. Comonwealth Edison Company VICE- PRESIDENT'S INSTRUCTION No. 1-0-17 dated October 22, 1979, pemits a senior operator to deviate from technical specifications and withdraw a safety systen from operation. I inforr.ed Mr. O'Connor by a Comonwealth Edison DEVIATION REPORT dated September 4,1980, that Comonwealth Edison creates a substantial safety hazard operating nuclear power plants at Dresden, Quad Cities, and Zic.. stations. '
I notified Mr. Victor Stello, Director. Of fice of Inspecticn and Enf orce- i ment, U.S. Nuclear Regulatory Comission that Comonwealth Edison Company creates a substan\ial safety hazard operating nuclear plants at Dresden, Quad Cities, and Zivo notiuhs. I notified Mr. Stello that Commonwealth Edison Company creates a st.bstantial safety hazard by authorizing operators at company nuclear plants to deviate from technical specifications and withdraw safety systems fecm operation by the company's VICE-PRESIDENT'S INSTPUCTION No.1-0-17 of March 1,1931. I notified Mr. Stello by letter dated July 2, 1981.
I wrote to Mr. Stello & seccrd tine. In a letter d6ted Noverbcr 17, 1981, I inforred Mr. Stello again that Comrwealth Edison Company creates a substantial safety hazard by authorizing operators to deviate from technical '
specifications and withdraw safety systems frem operation at Dresden Quad Cities and Zion stations.
The changes to Federal Regulations which permit a senior operator to depart from technical specifications when operating a corrercial nuclear pher plant in an enargency, becare effective June 1, 1983. In justifying the changes, you were told that er.ergencies can arise during which compliance with a license coridition or a technical specification could prevent necessary action to protect public health and safety. Public health and safety are protected frcm a comrercial nuclear pcwer plant's radiation by plint design, t
Plant design ensures the integrity cf physical barriers which prevent the uncontrolled release of radioactivity. Operating the nucleer plant within safe y limits ensures the integrity of these physical barriers. Compliance with technical specifications during an emergency requires an operator to (1) operatt with the reactor's automatic protective devices set to function to J correc : an abnormal plant condition before a safety limit is reached; (2) operat t with safety equipment ready to perform as designed to keep the plant within safety limits during an emergency.
emitting a nucle;r plant operator to deviate from technical specifica.
tionf risks exceeding a safety limit and betaching a barrier designed to prevent the uncontrolled release of radioactivity. To protect public health and safety from the uncontrolled release of radioactivity from a corrercial
Or. Nunzio J. Palladino Page 3 ,
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. nuclear power plant, direct nuclear plant operators to follow technical specifications; do not permit nuclear plant operators to deviate from tech;.1-cal specifications.
You were also told that the Special % .ew Group Office of Inspection and Enforcement en Lessons Learned from Three Mile Island, recommended the new rule. The Special Review Group wrote that actions such as releasing radioac-tive gas in greater concentration than permitted by technical specifications, might sometimes be justifiable. The Special Review Group recomended against giving blanket relief from technical specifications during an accident, however. The Special leview Group found that there would have been no acci-dent at the Three Mile Island if technical specifications had been followed.
Information on the Special Review Grour 's findings comes from paragraph 3.5 of NUREG-0616. l The General Prudential Rule for ships at sea is quoted as being similar to the new rule permitting a senior operator in a commercial nuclear power plant to depart from technical sper,ifications in an emergency. The Rules of the Road are rules for steering ships, rules for lookouts, lights, and other signals. The rules are designed to prevent ships from Colliding. The General Prudential Rule permits the captain of one ship to deviate from the rules if the capt61n of another ship is cauting drnger by violating the rules. A nucicar plant's technical specifications are different kinds of rules.
Technical specifications deal with :hysical principles. Technical specifica- <
tions are rules to ensure that operitors operate and maintain proper physical l conditions within the power plant. Operating and maintaining pecper physical conditions in the power plant--desi;n pcwer lev sis, Lerperatures, pressure, and reactor coolant systea ficas--e sures the ircegrity and safety of the nucler.c plant, ,
The General Prudential Rule applies to navigating ships at sea and in inland waters. The Rule does not apply to the operation of the nuclear power plant of a nuclear powered ship.
The Federal Aviation Administration rule,14 CFR 91.3, is quoted as being similar to the new rule. The Federal Aviation Administration rule permitt an aircraf t pilot to apply basic aerodynamic principles and deviate from a !
Federal Aviation Administration rule when necessary to avoid endangering his r aircraft. For exarple, it wculd be wrong to require an aircraf t pilot to attempt to maintain assigned altituce when experiencing serious engine prob.
lems. A nuclear plant operator is applying basic physical principles when following technical specifications so he should not be permitted to deviate from these rules.
When an operator, operating a commercial nuclear pcwer plant, departs from technical specifications, he:
(1) operates the nuclear reactor with process variables--reactor power, reactor coolant flows, reactor coolant temperature, reactor coolant p essure--outside safety limits, or (2) turns off or changes the settings for the automatic protective devices designed to correct an abnormal plant condition before a safety limit is reached, or (3) turns off or shuts down equiprent required for the safe operation of ,
the nuclear reactor. [
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- Dr. Nunzio J. Palladino Page 4
- Technical sped fications are defined in the Code of Fe h ral Regulations, l, 1", CFR 50.36:
To protect public health and safety from the uncontrolled release of radioactivity from a commercial nuclear power plant, direct the licensee of a nuclear plant to manage the plant to operate in accordance with the plant's Operating License and Technical Specifications.
In my letter of May 3, 1984, I urced you to:
(1) Cancel the new Federal Regulations, which permit the license of a comercial nuclear power plant to deviate from tec:'.nical specifica-tions in an emergency 10 CFR 50.54 (x) and (y),
(2) Tell the president of General Public Utilities Nuclear Corporation that you expect him to promulgate policy that Three Mile Islaric Unit 1 is to be m crated in ar.cordance with the Operating License and Technical 5,9cifications, (3) Have Nuclear Regulating Cornission inspectors inspect Three Mile Island Unit 1 to ensure that the president of General Public Util-ities Nuclear forporation has implemented policy to operate Unit 1 in accordance with the Operating License and *echnical Specifica-tions.
(4) Have a Nuclear Regulatory Comission inspector inspect Three Mile Island Unit I daily to verify that the nuclear plant is being operated in accordance with the Oparating License and Technical Specifications. Have an inspector inspect daily and report results to the Regional Atinistrator.
This letter is written to reaffirm these recorcendations.
Sincerely yours,
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Charles Young Copy to:
Thomas M. Roberts, Commissioner U.S. Nuclear Reguletory Comission Washington, DC 20555 Victor Gilinsky, Comissioner U.S. Nuclear Regulatory Conniasion Washington, DC 20555 James K. Asseltine, Cominioner U.S. Nuclear Regulatory Comission Washington, DC 20555 Frederick Bernthal, Cornissioner U.S. Nucleer Regulatory Comisston Washington, DC 20555
262 Sheffield Lane Glen Ellyn, IL 60137 s July 17, 1984 Dr. Nunzio J. Falladino Chairman U. S. Nuclear Regulatory Comission Washington, D. C. 20555 l
Dear Mr. Chairman:
I hereby inform you that you have created a substantial safety hazard in the operation of commercial nu-lear power plants in the United States. You amended Federal Regulations for operating commercial nuclear power plants.
You now permit a senior operator operating a commercial nuclear pcwer plant to depart from plant Technical Specifications. You permit a senior operator operating a commercial nuclear power plant to withdraw a safety system from operation.
The Atomic Energy Commission did not permit cperators operating comercial nuclear power plants to withdraw a safety system from operation. An Operating License issued by the Atomic Energy Comission required a utility to oper6te the nuclear plant in accordance with plant Technical Specifications.
You have amended the Code of Federal Regulations, 10 CFR 50.57, by issuing new regulations 10 CFR 50.54 (x) and (y). Federal Regulation 10 CFR 50.57 requires the licensee of a comercial nucinr power plant to operate the plant in accordance with plant Technical Specifications. Federal Regulations 10 CFR 50.54 (x) and (y) relieve the licensee of this responsibility.
I have inforced authorities in the past that permitting an operator operating a comercial nuclear power plant to deviate from Technical Specifications and withdraw a safety system from operation creates a substantial safety hazard:
(1) I informed Mr. James J. O'Connor that Comonwealth Edison Conpany creates a substantial safety hazard operating nuclear power plants at Dresden, Quad Cities and Zion stations by permitting operators to with-draw a safety system from operation. I informed Mr. O'Connor by a Comonwealth Edison Company DEVIATION REPORT dated September 4,1980.
Mr. O'Connor is president of Commonwealth Edison Company.
(2) ! informed Mr. Victor Stello that Comonwealth Edison Company creates a substantial safety hazard operating nuclear power plants at Dresden Quad Cities and Zion stations by permitting cperators to with-draw a safety system from operation. I informed Mr. Stallo by letter dated July 2, 1981. Mr. Stello was Director, Office of Inspection and Enforcement, U. S. Nuclear Regulatory Comission.
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Dr. Nunzio J. Palladino July 17, 1984 Page Two (3) I informed Mr. Stello again that Convenwealth Edison Company creates a substantial safety hazard operating nuclear power plants at Dresden, Quad Cities and Zion stations by permitting operators to withdraw a safety system from operation. I informed Mr. Stello by letter dated November 17, 1981.
I am informing you that you create a substantial safety hazard by permitting operators operating commercial nuclear power plants in the United States to withdraw a safety system from operation. I am informing you in accordance with the Code of Federal Regulations, Part 21.
Sincerely yours,
) /t ,1.t . bj - s, Charles Young ,;)
cc: Mr. Thomas M. Roberts, Commissioner U. S. Nuclear Regulatory Connission Washington, D. C. 20555 ftr. James K. Asselstine, Cormissioner U. S. Nucicar Regulatory Cecmission l
Washington, D. C. 20555
! tir. Frederick Bernthal, Commissioner U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i
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[d';. m j. .I'S NUCLEAR REGULATORY COMMISSION UNITED STATES 3 W ASHING TON, D. C. 20656
,* ..** )* JUL 31 %
Mr. Charles Young 262 Sheffield Lane Glen Ellyn. Illinois 60137
Dear Mr. Young:
Your June 14, 1984 letter to Chairtnan Palladino in which you commented on the regulation 10 CFR 50.54(x) and (y) which permits deviations from terh-nical specifications in an emergency, and asked that it be cancelled has been referred to me for reply.
I would like to emphasize that the rule cannot be invoked by a licensee et will. Specific circumstances must exist before the rule can be used and controls exist to prevent abus D hese are set out below:
- 1. An emergency situation must exist.
- 2. Licensee action must be reasonable.
3.- The actior, taken must be immediately needed to protect the public health and safety.
4 No action consistent with the license that can provide adequate or ecuivalent protection is immediately apparent.
- 5. Licensee most innediately notify NRC via the dedicated i
phone lines.
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- 6. The action mun be approved, as a minimum, by a licensed senior operator.
The rule makes it clear that the burden for safe operation and proper action that may be needed to protect the public health and safety in an emergency rests with the licensee. With this rule, a licensee cannot excuse itself from responsible action en the basis that the license prevented it.
On balance, we believe the rule is worthwhile and an improvement to safety and therefore should be retained.
Sincerely.
[ W Harold R. Denton, Director Office of Nuclear Reactor Regulation p H - c ri s ,i n A O_
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Glen Ellyn, IL 60137 August 6, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Denton:
In your July 31st letter, you write that the new Federal Regulation which permits a licencee to deviate from technical specifications when operating a nuc'. ear plant Nild be retained. The Three Mile Island Unit 2 operator deviated fror., nical specifications at 0403 the morning of Ma.ch 28, 1979.
The nuclear plant operator turned of f an emergency signal and shut down the emergency core cooling system.
You cite specific circumstances which nust exist before the licensee of a commercial nuclear power plant is to deviate from technical specifications.
An emergency existed at Three Mile Island the morning of March 28, 1979. An emergency existed and Three Mlle Island's licensed senior operator approved the action of the nuclear p' . ant opt.rator. The senior e,)erator thought that it was reasonable to turn off the emergency signal and shut denn the argency core cooling system because it was not immediately apparent to him that following technical specifications was providing protection. It was not ,
inrediately apparent to the senior operator that following technical specificatior.s was needed to protect the rablic health and safety. It ns not innediately apparent to him that fuel design limits might be exceeded threatenir.g a barrier designed to prevent the release of radioactive fission products and prote:t public health and safety. Fuel design limits were ;
l exceeded. A barrier designcd to prevent the release of fission products was i l breeched thereby threatening the health and safety of the public.
l Region I of the Nuclear Regulatory Comission was notified about the accident [
' at 0845, March 28,1979. At 0845, reactor coolant system cressure was below i l the set point of the emergency core cooling system but the eurgency core l cooling system was shut down. The licensee continued to duiate from techni-cal specifications. Fuel design limits had been exceeded, fission products had been released and the health and safety of the public threatened.
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Mr. Harold R. Denton, Director August 6, 1984 ;
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If Three Mile Island's senior operator had followed the plant's technical specifications at 0403, March 28, 1979, there would have been no accident at Three Mile Island. The nuclear rcactor would not have been wrecked and the health and safety of the public eculd not have been threatened.
Your change to Federal Regulations permits a senior operator operating a commercial nucicar power plant to turn off an emergency signal and shut down a safety system. Serious accidents at: 'tkely at nuclear power plants if operators turn off emergency signals and shut down emergency systems. Serious accidents are likely at nuc' ar power plants if licensees deviate from techni-cal specifications as now pt :ted by Federal Regulations.
Again I t:;e you to cancel Federal Regulations 10 CFR 50.54 (x) and (y) and require licensees to follow terinical specifications when operating commercial nuclear power plants.
Sincerely yours,
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Charles Youn'g <I 1
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f[,.o Ts- esgk' UNITED $TATES NUCLEAR REGULATORY COMMISSION i 5 WASHINGTON, D. C POSM
- 5 e....f AUG 2 31984 Mr. Charles Young 762 Sheffield Lane t Glen Ellyn, Illinois 60137
Dear Mr. Young:
Your letter of July 17, 1984 to Chairman Palladino regarding the regulation that permits deviations from technical specifications in an emergercy has been referred to me for reply, t The similarity of this letter to an earlier letter from you dated June 14, i i
1984 (also to Chainnan Palladino) suggests that you may not have ruefved my response to your earlier letter which was dated July 31, 1984. A copy [
of that response is enclosed which also servos as our response to your i recent July 17 letter. l Sincerely. .
2f.
M' ' 7Har
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- s. Denton,
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Director
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Enclosure:
NRC letter dated - l July 31,1984 j I
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