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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 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 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 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 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 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 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 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 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 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 ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates 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 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 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 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 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 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 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 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 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 ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates 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 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 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 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 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 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 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 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 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 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 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 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] |
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_ .
e s OPU Nuclear Corporation
.. , UQg3 f Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7021 TELEX 84 2386 Writer's Direct Dial Nurnber:
(717) 948-8005 January 29, 1993 C311-93-2011 l
U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50, Docket No. 50-289
" Reply to a Notice of Violation" - Inspection Report 92-20 In accordance with 10 CFR 2.201, this letter transmits the GPU Nuclear response to the Notice of Violation identified in Enclosure I to Inspection Report 92-20. After a review of the matter, GPU Nuclear disagrees with the statement that sets forth the basis for the Notice and denies that a violation occurred. Attachment 1 3rovides a detailed response to the Notice of Violation including the ) asis for disputing the violation.
Based on NRC Staff. discussion in Inspection Report 92-20 (Section 5.3), GPU Nuclear understands that the Staff intended for " missed surveillance" information to be data to be gathered using the LER rule (10 CFR 50.73).
Therefore, for purposes of accuracy of the record )ending resolution of the issue of reportability under the current THI-l Tec1nical Specifications, GPUN Nuclear is filing a " voluntary LER" addressing the subject missed surveillance.
$gm 050002 7,c,Brou$1on 8@ Vice President and Director, THI-1 mo- AWM/ emf
, rw g Attachment 7
jf cc: THI-) Senior Project Manager
-Region I Administrator.
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.@h TMI Senior Resident Inspector fr }i GPU Nuclear Corporation is a subsidwy of General PutAc Ut:i$es Corporation -
METROPOLITAN EDISON COMPANY
. JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRICAL COMPANY GPU NUCLEAR CORPORATION Three Mile Island Nuclear Station, Unit 1 (THI-1)
Operating License No. DPR-50 Docket No. 50-289 Reply to Notice of Violation in Inspection Report 92-20 This letter is submitted in reply to the Notice of Violation in Inspection Report 92-20. Routine Monthly Inspection of THI-l covering the period October 27, through December 7, 1992, dated January 6, 1993. All statements contained in this reply have been reviewed, and all such statements made and matters set torth therein are true and correct to the bes* of my knowledge.
I N T.G.Broughtgn Vice President and Director, THI-l Signed and sworn before me this M day of b%AanhL ,1993.
N h E n ~ ~ M 24 6 3 o Notary Public EM M P Rdc
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C311-93-2011 Page 1, t'
ATTACHMENT 1 NOTICE OF VIOLATION 10 CFR 50.73(a)(2)(1)(B) states that the licensee shall submit a Licensee Event Report (LER) within 30 days after the discovery of an operation or condition prohibited by Technical Specifications. Technical Specification 4.1.2 states that equipment sampling and testing shall be performed as detailed in Tables 4.1-2 and 4.1-3. Table 4.1-3, item 3, requires a monthly determination of boron concentration on the core flood tanks.
Contrary to the above, on January 23, 1992, the Licensee did not submit an LER within 30 days after the discovery of an operation or condition prohibited by Technical Specifications. On December 23, 1991, the licensee discovered that the i core flood tanks had not been sampled by December 21, 1991, to determine boron concentration.
This is a Severity Level V violation (Supplement I). ,
GPU NUCLEAR RESPONSE TO THE NOTICE OF VIOLATION GPUN denies that the violation occurred. While-the facts are not in dispute, GPUN ,
required does not agree of the submission with anthe LERStaff conclusion in this situation.thatIt 10 CFR 50.73 is agreed that(a)(2)(i)(B)dthe cite vio1' tion ;
is of minor safety significance, and GPUN is open to the prospect of.-amendint. the THI-1 Technical Specifications (T.S.) to clarify the reporting requirements, 'f that is necessary and appropriate. There is no interest in-withholding- i information from the Staff. As-ex)lained below, however, GPUN made a good faith and reasonable interpretation of tie requirements at the time. Where the-inspector subsequently disagrees with the GPUN reportability evaluation and bases that disagreement upon Staff guidance which has been, we submit, ambiguous if not inconsistent, GPUN respectfully disagrees that'use of NRC Enforcement Policy is -
now appropriate as a means to clarify the requirement.
The facts surrounding the missed core flood tank sampling surveillance are-accurately described in section 5.3 of_NRC' Inspection Report 92-20. On December 23, 1991, GPUN identified that the monthly sample -- which under the T.S.
was to have been~taken.no later than December 22, 1991 at-4:40 a.m. -- had been missed. The tanks were sampled December 23, 1991, and the boron concentrations-met -T.S. limits. The TMI-l Plant Review Group 002 show that'the missed surveillance was evalua(PRG) ted as minutes' a potentially for Meeting No. 92 reportable event. The'PRG minutes conclude that:.
Since the-sample results determined the boron concentration to be within the. limits of the LCO, no operation'or condition prohibited by Technical
- Specifications occurred.and this event' is ~not reportable' under 10 CFR
- 50.72 or 50.73.-
E_ - __ _ , _ _ _ ,, . ., _-. -_ .. _ . - , . _ _ ~ - ..
l . .
C311-93-20ll Page 2,
! During an inspection approximately eleven months later, the inspector reviewed these PRG minutes and, according to the inspection report:
On December 1, 1992, the inspector with the aid of the NRR Project Manager .
referred this specific situation to the NRC Technical Staff for their l understanding of the intent of the data that is collected by the LER rule.
The NRC Technical Staff considered missing a survoillance interval information that the NRC Staff desired to gather using the LER rule (10 CFR 50.73). (See NRC Inspection Report 92-20, at pp. 5-6.)
The report then proceeds to discuss Generic Letter (GL) 87-09 and the THI-l T.S., ;
and states: " Based on this information, the inspector disagreed with the PRG's reportability evaluation."
- it is informative to know that some Staff may now " desire" to gather this information under the LER rule. However, that interest cannot now constitute a
, basis for enforcement action where the asserted " requirement" is so ambiguous and subject to interpretation. GPUN believes that the PRG assessment was at the very least based upon a rational and reasonable interpretation of the NRC regulation and TH1-1 T.S.
The regulation in question,10 CFR 50.73(a)(2)(1)(B), requires a licensee to report "[a?ny operation or condition prohibited by the plant's Technical S)ecificat<ons." Neither this nor any other part of the LER rule (50.73) requires
- tie reporting of an event simply because a T.S. has been violated. Rather, the LER rule specifies the criteria for the types of events and conditions which are to be reported to the NRC. The words " operation or condition prohibited by the plant's Technical Specifications," have always defined a smaller, more specific class of circumstances than any violation of a plant T.S. In this case, the fact that the surveillance frequency T.S. had been violated did not automatically mean that an operation or condition prohibited by the T.S. had occurred.
As reflected in the PRG minutes, GPUN looked at whether a Limiting Condition for Operation had been violated, and concluded that the Core Flood Tanks had not been
- inoperable, and that the event was not reportable because no operation or
- condition prohibited by the T.S. had occurred. The conclusion that the THI-l T.S.
do not require a system / component to be considered IN0PERABLE immediately upon discovery of a failure to perform a surveillance requirement within the specified time interval is based upon THI-l Specification 4 (Surveillance Standards), the introductory paragraph to which states:
During Reactor Operational Conditions for which a Limiting Condition for Operation does not require a system / component to be operable, the associated surveillance requirements do not have to be performed. Prior to declaring a system / component o;)erable, the associated surveillance requirement must be current. The above applicability requirements assure the operability'of systems / components for all Reactor Operating Conditions when required by the Limiting Conditions for Operation.
- . - . _ - _ = . - _ - - ._ - _- . _ _ - _ - . -- .
4 C311-93-2011 Page 3, L i
Since the immediate performance of the recuired surveillance demonstrated the 4 continued o)erability of the equipment anc there was no technical reason to speculate t1at the equipment was not operable prior to the performance of the surveillance, the equipment is considered to have been OPERABLE during the period for which the surveillance was late.' The THI-1 PRG concluded that the equipment 2 was OPERABLE and there had been no " operation or condition prohibited by the plant's Technical Specifications" reportable under 10 CFR 50.73(a)(2)(1)(B),
4 This constitutes the basis for the PRG reportability evaluation which, in the view
] of GPUN, was correct and, at a minimum, is reasonable on its face and undeserving of enforcement action. Subsequent research into the LER rule and Staff statements on it confirms that conclusion.
The history of the !ER rule supports the PRG evaluation. As proposed, the parent of the regulation at issue was labeled section 50.73(a)(4), and as noted at 47 i federal Register 19543, 19546 (1982) required reporting of:
l Any event for which plant Technical Specifications require shutdown of the
- nuclear power plant or for which a plant Technical Specification Action Statement is not met.
The referenced FR Notice explained that:
... this paragraph includes events where the licensee should have shut down the reactor because of a condition that violated the Technical Specifications, and either -
(a) did not recognize until later review that the situation violated
- Technical Specifications and, therefore, did not shut down; or (b) did not recognize until later review that the condition existed and, therefore, did not shut down.
Thus. operation of the. plant with a condition that is orohibited by the Te_chnical Specifications should be reported (emphasis added). In addition, if a condition that would have required a )lant shutdown exists for a period of time longer than that permitted by tie Technical Specifications, it should be reported even if the condition was not discovered until after the allowable time had elapsed and the conditica was rectified immediately after discovery.
Here, the NRC established that operation with a condition prohibited by plant T.S.
meant events which should have resulted in plant shut down because of a T.S.
violation, but did not. result in shut down.
The second sentence of the Specification applies prior to placing a system / component into service initially or following removal from service.
The NRC also explained in the referenced FR N.tice that " failure to comply with a Surveillance Requirement need n7t be reported as an LER."
C311-93-2011
, Page 4, i
When promulgated in 1983 at 48 federal Register 33850, 33855 (1983), proposed
- section 50.73(a)(4) became section 50.73(a)(2)(i), and was given its present '
wording, which requires reporting of (A) The completion of any nuclear plant shutdown required by the plant's Technical Specifications; or j (B) Any operation or condition prohibited by the plant's Technical Specifications ...
The accompanying Statement of Considerations for the referenced FR Notice explained that:
This paragraph has been reworded to more clearly define the events that must be reported. In addition, the' scope has been changed to require the reporting of events or conditions " prohibited by the plant's technical specifications" rather than events where "a plant Technical Specification Action Statement is not met." This change accommodates plants that do not have requirements that are specifically defined as Action Statements.
This paragraph now requires events to be reported where the licensee is required to shut down the plant because the requirements of the
. Technical Specifications were not met.
. In addition, if a condition that >is )rohibited by the T.S. existed (i.e., the plant was in a degraded mode all( <ed )y the T.S.) for a period of time longer than that permitted by the T.S., it must be reported even if the condition was not discovered until after the allowable time had elapsed and the condition was i
rectified immediately after discovery. M.; NUREG-1022 (Licensee Event Report System, 1983) at page 11.
4 These revisions did not change the fundamental concepts of the regulation as originally proposed -- i.e., " operation or condition prohibited by the plant technical s)ecifications" means operation when a T.S. requires plant shutdown or a condition w1ere the plant is in a degraded mode for a period of time longer than the T.S.. permit. Since the TMI-l T.S. did not require a plant shutdown for the missed surveillance and the plant was not in a degraded condition, section 50.73 did not apply here.'
l Since the inspection report cites Staff guidance -- in addition to the regulation and the TMI-l license -- GPUN has examined that guidance also. Nevertheless, it must be noted that a " regulatory requirement," in the context of enforcement action, "means a legally binding requirement such as a statute, regulation, license condition, technical specification, or order." (10 CFR Part 2, Appendix C,n.2.) Staff guidance alone cannot establish a legally binding requirement.
l l
l l
l Plants which operate with Standard Technical- Specifications have specific technical specifications which make compliance with surveillance intervals necessary to meet OPLAABILITY requirements for a system / component. In their case, section 50.73(a)(2)(1)(B) would require that an LER be submitted for a late surveillance.
C311-93-20ll Page 5 In the inspection Report, at page 6, the Staff relies upon GL 87-09, which is entitled, " Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of limiting Conditions for Operation and Surveillance Requirements." This guidance addressed a few problems encountered with the STS.
While it was sent to all licensees and applicants the T.S. changes proposed and encouraged were described as " voluntary for all IIcensees and current OL applicants." THI-l does not have STS and did not adopt the changes described in GL 87-09.
One of the problems addressed in GL 87-09 was " Unnecessary Shutdowns Caused by inadvertent Surpassing of Surveillance Intervals (Specification 4.0.3)." STS 4.0.3 stated that the failure to perform a surveillance within the specified time interval shall constitute a failure to meet the LCO's Operability Requirements.
The Staff observed in GL 87-09 (p. 4) that it was " overly conservative to assume that systems or com)onents are ino)erable when a surveillance requirement has not been performed." Tierefore, a 24-lour period was 3roposed to perform a missed surveillance before shutdown requirements apply. .iaving rectified the OPERABILITY harshness of the STS, the Staff proceeded nevertheless (GL 87-09, p. 5) to attempt to retain the LER requirement without amending the rule: "the failure to perform a surveillance within the allowable surveillance interval defined by specification 4.0.2 constitutes a reportable event under 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plants' TS." No effort was made to explain or support this deviation from the fundamental concepts upon which section
- 50.73(a)(2)(1)(B) was adopted.
A second generic letter , GL 91-18, addresses operability and includes a section 6.6, " Missed Technical Specification Surveillance." That section quotes STS 4.0.3, and advises that "(p]lant-specific Technical Specification (TS) variations of this statement may exist, in which case the plant-specific TS govern." (GL 91+18, p. 12.) This confirms that the TMI-l license must be applied as it is written. Nevertheless, it is noteworthy that GL 91-18 appears to change the Staff view expressed in GL 87-09. While the letter states that "[f]ailure to perform a TS requirement within the specified time interval is considered a condition prohibited by the IS and is reportable at least under 10 CFR Part 50.73," it also appears to interpret the time intervals meeting the requirements to include the 24-hour delay period which starts with discovery of a missed surveillance. While ambiguous, GL 91-18 could be read to require an LER, for those with amended STS, only where the 24-hour period is exceeded.
In September 1992, the NRC published Standard Technical Specifications for Babcock & Wilcox plants as NUREG-1430. Surveillance Requirement SR 3.0.1 states in part that "(f shall be failure]ailure to meet to perform the LCO a Surveillance except as providedwithin the3.0.3" in SR specified SRFrequency 3.0.3, in turn, states:
If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LC0 not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less.
The Bases for SR 3.0.3 states that "[c]ompletion of the Surveillance within the delay period allowed-by the Specification, or within the Completion Time of the-ACTIONS, restores compliance with SR 3.0.1." (NUREG-1430 (Rev. O September 28, 1992), at 3.0-3, 4; B 3.0-12.) Consequently, it would appear that under the most recent Staff-approved T.S.,. a missed surveillance performed during the delay .
period is not reportable.
. 4.
C311-93-20ll Page 6 in conclusion, since GPUN complied with section 50.73, as it reasonably should be interpreted to apply specifically to the THI-I T.S., no LER was required and a
- violation did not occur. Staff guidance cannot be used in an enforcement context 1 to add a new requirement out of an unchanged regulation. Further, Staff guidance has been ambiguous and now would appear not to require an LER for a missed ,
surveillance successfully completed during the delay period.
Corrective Actions Taken and Results Achieved
. As stated at the outset, GPUN does not wish to withhold from the Staff information 3
which the NRC desires to fulfill its regulatory functions. Consequently, GPUN is filing a voluntary LER on this event. In addition, an Interim THI-1 Policy was issue ( in January 14, 1993 which instructs THI-l staff to submit a voluntary LER
- on eatn missed Technical Specification Surveillance until further notice.
In the longer term, GPUN seeks to achieve a common understanding of and clarity in (1 .While the inspection 1
the reporting report states requirements the desire of under some section 50.73(a)(2) to receive information)(B).
on missed surveillances under the LER rule, the recently issued B&W Standard Technical Specifications, if j adopted by THI-1, would appear not to have required an LER in this case.
Therefore, prior to proposing any changes to the THI-1 Technical Specifications (e.g., to specify the OPERABILITY consequences of a late surveillance and to provide a delay period), GPUN will undertake a dialogue with the Staff to obtain
, clarification on the interpretation of various technical specification provisions which might be pursued.
Corrective Actions to Avoid Further Violat_iani Although GPUN denies that a violation occurred, an Interim Policy was published on
' January 14, 1993, which should avoid further violations concerning reportability for missed surveillances under the provisions of 10 CfR 50.73 pending clarification of the relevant reportability requirements and communication of the same to the licensee.
Date of Full Compliance GPUN has been and remains in full compliance.
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