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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
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GPU Nuclear. inc.
( Rout, "1 South NUCLEAR Post Office Box 480 Middletown. PA 17057-0480 Tel 717-944 7521 December 24, 1998 1920-98-20716 l
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Reply to Notice of Violation Dated October 15,1998 - Supplement i The purpose of this letter is to supplement the November 12,1998 GPU Nuclear reply'to the NRC's Notice of Violation (NOV) dated October 15,1998. This is in response to a request from NRC Region I inspector Jimmi Yerokun on December 9,1998 for GPU Nuclear to desciibe our reasons for I changing the normal Makeup and Purification /High Pressure Injection (Makeup / HPI) System valve I lineup and the basis upon which we found that change to the operating procedures acceptable. The following presents some ofthe background regarding the need for this change and a sununary of the GPU Nuclear safety evaluation (Reference 1) that approved the change.
f' BACKGROUND: l
[ The HPI system function as described in the Final Safety Analysis Report (FSAR) is to provide emergency core cooling for conditions when Reactor Coolant System (RCS) pressure is above the
- l. Low Pressure Injection (LPI) System capability. A simplified diagram of the applicable portion of the l Makeup (Mi D System valve a.rangement is shown in Figure 1 (Attached).
Until TMI-l Operating Cycle 12 which began in October 1997, the Makeup Pump suction header was lined up for nonnal plant operation with only one of the two sets of cross-connect valves (MU-V-68A and MU-V-68B) open between the suctions of the three Makeup Pumps. Makeup Pump MU-P-1B is normally operating taking suction from the Makeup Tank (MUT) to provide a source for nonnal RCS e ,? -ny l
9901060096 PDR 981224 7)
ADDCK 05000289 G PDRd
1920-98-20716 Page 2 of 5 makeup and Reactor Coolant Pump (RCP) seal injection. MU-V-14A and MU-V-148, which must be closed during normal operation to prevent injection ofborated water from the Borated Water Storage Tank (BWST) into the RCS, both open automatically on an Emergency Safeguards (ES) Actuation Signal. Prior to Operating Cycle 12, MU-P-IC was aligned for ES operation along with MU-V-14B, ,
but the MU-P-lC suction header was isolated from the common suction header for MU-P-1 A and !
MU-P-1B with MU-V-69A and MU-V-698 locked closed.
GPU Nuclear had been considering the change to operate with a common Makeup pump suction l
header for some time. The assessment of safety consequences and implications of a June 1985 '
inadvertent Emergency Safeguards Actuation System (ESAS) actuation, reported as LER 85-001, j concluded that if the event had occurred on the "B" side without the MU-P-lC suction valves '
first being opened, the event could have resulted in damage to Makeup Pump MU-P-lC (Reference 2). In a follow-up study, the improvement in Makeup Pump availability from maintaining both sets of suction cross connect valves open was evaluated. The study found that a l reduction in the calculated core damage frequency (CDF) could be achieved and recommended further consideration of making that change. This was reported to the NRC in 1989 (Reference 3).
During the TM1-1 Architect Engineer (AE) Engineering Design Inspection (50-289/96-201),
w hich ended in January 1997, the inspection team raised issues because of the fact that the MU-P-lC suction piping is not normally lined up to a source of water. The repon states in Open !
Item (01) 96-201-02 that in the normal standby mode, the suction from the BWST and high pressure injection valve from makeup pump MU-P-lC are in the closed position, and the pump is isolated from the suction and discharge headers that are connected to makeup pumps l l
MU-P-1 A&B and the Makeup Tank (MUT). Since Makeup Pump MU-P-lC is not lined up to any water source until MU-V-14B opens and there are no interlocks or time delays, the inspection team was concerned that the effect on the pump due to a slow opening suction valve combined ;
with a rapid start of the pump and a fast opening high pressure injection valve had not been I properly analyzed. Also the report states in O! 96-201-03 that the inspection team identified a potential for accurnulation of non-condensables, such as hydrogen, released from the stagnant water in the suction line because of the physical configuration of the line and considered that a positive pump suction pressure was not necessarily an indication of absence of gas accumulation i in the piping.
In February 1997 GPU Nuclear discovered that Makeup suction piping and components had potentially been stressed beyond design code allowable stresses on a number of occasions over a long period of time due to leakage through the Makeup Pump recirculation line check valves.
Having completed the safety evaluation for the change, GPU Nuclear committed in LER 97-003, Revision 1 to implement changes prior to the next operating cycle (TMI-1 Operating Cycle 12) to eliminate the possibility of over-pressurizing the Makeup suction piping during testing by changing the normal valve lineup for the Makeup System to maintain the Makeup Pump suction cross connect valves (MU-V-69A and MU-V-69B) open (Reference 4).
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1920-98-20716
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PURPOSE OF THE CHANGE:
The following lists some of the benefits of the change to maintain the Makeup Pump suction cross H
connect valves (MU-V-69A and MU-V-69B) open:
l 1. Concerns associated with maintaining an isolated Makeup Pump suction header filled and vented are resolved. Maintaining cross connect valves (MU-V-69A and MU-V-698) open:
- a. Provides greater assurance that the Makeup Pump MU-P-lC suction piping remains filled and l vented at di times, b.- Precludes damage to Makeup Pump MU-P-lC ifit were inadvertently started during l operation or testing without establishing a suction path from the MUT or the BWST, ;
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- c. Reduces the potential for damage to Makeup Pumps MU-P-1 A & MU-P-1B due to a failure of MU-V-14A to open on ES actuation, and I
- d. Reduces the probability of Makeup Pump damage due to improper valve operations during Makeup System testing.
L 2. ' Resolves concerns associated with over-pressurization ofisolated Makeup Pump suction l piping and components during normal or emergency operation. This change eliminates the !
potential to over-pressurize the Makeup suction piping due to leakage through recirculation line L check valves or other leakage paths on the pump discharge. With a common suction header any flow back through an idle pump will picked up by the operating pump without any significant pressure increase in pump suction. This change resolves over-pressurization concerns during l normal or emergency operating as identified in LER 97-003.
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- 3. Results in a lower calculated core damage frequency due to a reduction in the probability of Makeup Pump damage and the resulting increase in MU/HPl System availability. This was l . the conclusion of the Probabilistic Risk Assessment (PRA). ;
l i SAFETY REVIEW:
1 The impact of operation with the Makeup pump suction cross connect valves open was evaluated using PRA methodology and the calculated core damage frequency was found to be lower if the !
suction cross connect valves are maintained open (Reference 3).
The potential effect of this change on Makeup Pump NPSH was evaluated. The design basis scenano i for Makeup Pump NPSH concern is an HPI line "B" break where the operator opens MU-V-217 and starts a second MU Pump in response to the reactor trip. During the period of time until the BWST
- valves (MU-V-14A/B) open, the MUT level & pressure and therefore NPSH available to the Makeup Pump is decreasing. The threat to the Makeup Pumps is terminated when ES actuates, which opens l MU-V-14-A/B, or when MU-V-14-A/B is opened by the operator. Operation with'a common suction header does not adversely effect this scenario. There is no procedure direction for the operator l- to start all three Makeup Pumps taking suction from the MUT. In fact, as part of the change in 1997, a
1920-98-20716 Page 4 of 5 Limit & Precaution statement has been added to the procedure (Reference 5) to specifically restrict such operations. When ES actuates all three pumps receive start signals, MU-V-14A and MU-V14B are signaled to open, and adequate NPSH is provided while the Makeup Pumps are drawing suction from the BWST. There is also adequate NPSH for three Makeup Pumps ifone MU-V-14 valve fails to open.
The potential for gas entrainment of the Makeup Pumps was evaluated because the change altered the operational configuration of the suction header. The evaluation considered the limiting design basis scenario where all three pumps are operating and MU-V-14A or MU-V-148 fails to open. The maximum MUT pressure curve is based on the minimum possible pressure in the Makeup Pump suction header when the minimum level in the BWST is reached. Operating limits on MUT pressure and level provide a conservative boundary to prevent gas entrainment with a common Makeup Pump suction header. In addition to the evaluated condition, the Abnormal Transient Procedures (ATPs) direct the operator to shift the Makeup Pump suction to LPI pump discharge prior to reaching the minimum level in the BWST. This adds conservative margin to the evaluation. The evaluated case for potential gas entrainment uses conservative assumptions and concluoes that adequate margin to gas binding of the Makeup Pumps is maintained by the specified initial conditions for pressure ad level in the MUT.
An evaluation of the single failure potential introduced by making the MUT (MU-T-1) a common HPl component was performed (Reference 7). Failure ofMU-V-27 or MU-V-28 to close, failure of MU-V-13 to close, failure of MU-V-18 to close, and Loss of DC power were among the failures considered in the evaluation. This evaluation concluded that the limiting case for potential gas binding is the failure ofMU-V-14A or MU-V-14B to open.
Maintaining the required Makeup Pump NPSH margin and the prevention of Makeup Pump gas entrainment during a LBLOCA are ensured by maintaining the MUT pressure vs. level relationship.
The instruments used to ensure these parameters (MUT level and pressure) are calibrated in accordance with QA program requirements and periodically MUT level (Reference 8) and pressure (Reference 9) are compared to independent instruments to verify their operability. This ensures that no single instrument failure will degrade the operator's ability to maintain the MUT pressure / level relationship and thereby ensure that the initial condition assumptions of the Makeup Pump NPSH and i gas entrainment analysis remain valid.
Loss of Coolant Accident (LOCA) analyses, which credit the capability of the HPI system, include consideration for a single failure. The effect of this change improves the HPI system performance using single failure assumption considerations. HPI system performance was evaluated in response to
- active failures of BWST supply valves (MU-V-14A or MU-V-148) or Decay Heat Removal (DHR) l Pump supply valves (DH-V-7A or DH-V-7B) when piggyback operation was required. With a
' LER 98-009 reported that, due to an analytical error, there was a potential for Makeup Pump gas entrainment to occur during a LOCA if either MU-V-14A or MU-V-14B were to fail to open on an ES actuation. Temporary procedural changes were implemented immediately which placed additional restrictions on the Makeup Tank temperature and pressure limits to compensate for that error. Subsequent to GPU Nucicar submittal of the LER (Reference 6), permanent changes have been implemented that resolve the issue.
i
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e i
1920 4 8-20716 Page 5 of 5 g
L . .
I common Makeup Pump suction header, either DHR Pump can provide suction to either or both L ' Makeup Pumps. This change does not effect the HPI system response to any other active component i L failures. HPI is not required to provide long term cooling in any design basis event where single failure l' has not already been taken. Passive failures of the Makeup System are beyond the design basis. The ;
l - Makeup System is not required for long term Reactor Coolant System boron concentration control.
[ CONCL,USION: j j In summary, maintaining the MU/HPI suction cross connect valves open during operation results in higher MU/HPI system reliability and a reduction in core damage frequency.
REFERENCES:
L 1. GPU Nuclear Safety Evaluation No. SE-000211-015, " Operation with MU Suction Cross -
L Connects Open," Revision 0, dated August 25,1997.
[. 2. G_PU Nuclear Letter No. 5211-85-2131, Hukill to NRC, "LER 85-001-0," dated July 26, l 1985.
L 3. GPU Nuclear Letter No. C311-89-2020, Hukill to NRC, "TMI-l Level 1 Probabilistic Risk l Assessment (PRA)," dated March 17,1989.
l ' 4.- GPU Nuclear Letter No. 6710-97-2423, Langenbach to NRC, " Licensee Event Report L (LER) No.97-003, Revision 1,". dated September 29,1997.
.5 Operating Procedure 1104-2, " Makeup & Purification System," (Current) Revision No. I 15, l l Effective December 18,1998. '
!: '6 GPU Nuclear Letter No. 1920-98-20519, Langenbach to NRC, "LER 98-009-00," dated September 18,1998.~
l
- 7. ' GPU Nuclear Safety Evaluation No.'SE-000211-024," Revised Makeup Tank Pressure and
' Level Limits," dated December 9,1998.
- 8. Surveillance Procedure 1301-1, " Shift and Daily Checks," (Current) Revision No.130, i Effective December 21,1998, u
9.' Surveillance Procedure 1301-4.1, " Weekly Surveillance Checks," (Current) Revision No. 66, l Effective June 10,1998.
Sincerely,
)
i i i
JamWN. Langenbach
- l. ,
Vice President and Director, TMI MRK' j l
O .cc: TMI Senior Resident inspector i TMI-l Senior Project Manager
' Region Administrator i File No. 97062
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