Letter Sequence RAI |
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MONTHYEARML20206H3571999-05-0606 May 1999
Forwards RAI Re 981203 Application & Suppls & 0416,requesting Review & Approval of Revised Core Protection SL & Bases for TMI-1 to Reflect Average of 20% of Tubes Plugged Per Sg.Response Requested within 10 Days of Receipt
Project stage: RAI
1999-05-06
[Table View] |
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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:OUTGOING CORRESPONDENCE
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
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
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
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
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
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
ML20212J0011999-09-27027 September 1999
Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted
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
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
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
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)
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
ML20209F2571999-07-0909 July 1999
Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1
ML20209G5861999-07-0909 July 1999
Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted
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
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
ML20196J5741999-06-30030 June 1999
Informs That as Result of Staff Review of Util Response to GL 92-01,rev 1,suppl 1,info Provided in Support of PT Limits License Amend & B&W Topical Rept,Staff Revised Info for Plant,Unit 1,in Reactor Vessel Integrity Database
ML20196H6811999-06-29029 June 1999
Forwards Insp Rept 50-289/99-03 on 990425-0605.No Violations Noted.However,Adequacy of Assessment of Reactor Bldg Emergency Cooler Operability Prior to Conducting Maintenance on One Reactor Bldg Spray Sys,Questionable
ML20212H8711999-06-21021 June 1999
Discusses Updated Schedule Commitment Submitted by Gpu on 990602 for Implementing Thermo-Lag 330-1 Fire Barrier C/As & Completion of Thermo-Lag Effort at TMI-1.Informs NRC Will Incorporate Commitment Into Co Modifying License
ML20195K2821999-06-17017 June 1999
Forwards Request for Addl Info Re Kinetic Expansion Region Inspection Acceptance Criteria
ML20212H6621999-06-0404 June 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Three Mile Island Nuclear Station
ML20207E7201999-05-27027 May 1999
Discusses Reorganization of Nrr,Effective 990328. Organization Chart Encl
ML20207B6541999-05-27027 May 1999
Forwards SER Accepting Util Program to Periodically Verify design-basis Capability of safety-related MOV at TMI-1 & That Util Adequately Addressed Actions Requested in GL 96-05
ML20207C0321999-05-18018 May 1999
Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co
ML20206S3411999-05-14014 May 1999
Forwards Insp Rept 50-289/99-02 on 990314-0424.Violations Occurred & Being Treated as non-cited Violations.Security Program Was Inspected During Period & Found to Be Effective
ML20206N5831999-05-13013 May 1999
Requests Description of Proposed Corrective Actions for Fire Zones AB-FZ-3,AB-FZ-5,AB-FZ-7,FH-FZ-2,CB-FA-1 & FH-FZ-6. Confirmation That Corrective Actions & Commitments Made Will Be Completed by 991231,requested
IR 05000298/19980091999-05-12012 May 1999
Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited
ML20206H3571999-05-0606 May 1999
Forwards RAI Re 981203 Application & Suppls & 0416,requesting Review & Approval of Revised Core Protection SL & Bases for TMI-1 to Reflect Average of 20% of Tubes Plugged Per Sg.Response Requested within 10 Days of Receipt
ML20207A5401999-04-29029 April 1999
Informs That Licensee 980930 Response to GL 96-06,appears to Be Reasonable & Appropriate for Specific Design & Configuration of RB Emergency Cooling at Plant,Unit 1 & That Staff Satisfied with Licensee Resolution of Waterhammer
ML20206D4001999-04-20020 April 1999
Informs of Completion of Review of Gpu Request for Exemption Submitted on 961231,970908,971230,980521,981014,981125 & 981223 from Requirements of 10CFR50,App R,Section III.G.2 for TMI Unit 1.Forwards Exemption & Safety Evaluation
ML20205S6791999-04-16016 April 1999
Forwards Insp Rept 50-289/99-01 on 990131-0313.No Violations Noted.Identification by Licensee Staff of Elevated Tritium Activity in Monitoring Well Led to Investigation & Identification of Leak from Buried Radwaste Path
ML20205P3391999-04-0909 April 1999
Discusses Results of Plant Performance Review for Three Mile Island Completed on 990225.Historical Listing of Plant Issues That Were Considered During PPR Encl
IR 05000289/19980061999-03-26026 March 1999
Ack Receipt of 981112 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-289/98-06 .Action Does Not Change NRC Determination That Change to Hpis Valve Configuration Involved URI
ML20204E3911999-03-17017 March 1999
Informs That Region I Plans to Conduct Open Predecisional Enforcement Conference to Discuss Apparent Violations Re Efs Issues as Described in Insp Rept 50-289/98-09,per
ML20204B6771999-03-15015 March 1999
Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors
ML20207H7391999-03-0505 March 1999
Forwards Insp Rept 50-289/98-09 on 981227-990130.Two Apparent Violations Being Considered for Enforcement Action.First Violation Deals with Failure to Follow Procedures for Control of Emergency Boration Source
ML20203F4911999-02-0505 February 1999
Forwards Request for Addl Info Re Licensee 981125 Amend Application Re TS Change Request 277 for OTSG Inservice Insp During 13R for Three Mile Island,Unit 1
ML20202H6771999-02-0303 February 1999
Documents Basis for NRC Staff Generic Approval of Requests to Relocate TS Requirements from Tss.Staff Generic SER Finding Relative to Relocated TS Requirements Encl
ML20196K3511999-01-22022 January 1999
Refers to Gpu Responses to Second NRC RAI Re GL 92-08 & Review of Gpu Analytical Approach for Ampacity Derating Determinations.Forwards SE & SNL Technical Ltr Rept Concluding That No Outstanding Safety Concerns Identified
ML20199H6471999-01-20020 January 1999
Forwards RAI Re Gpu TS Change Request 277 OTSG Cycle 13 for Plant Unit 1.NRC Has Determined That Addl Info Needed to Complete Review
ML20199G7401999-01-12012 January 1999
Forwards Insp Rept 50-289/98-08 on 981101-1226.No Violations Noted.Operator Workaround Program Found to Be Acceptable
ML20206S0221999-01-0808 January 1999
Responds to Re Changes to Physical Security Plan Identified as Rev 38,submitted Under Provisions of 10CFR50.54(p).Based on NRC Determination,Changes Do Not Decrease Overall Effectiveness of Security Plan
1999-09-30
[Table view] |
Text
m -
_t i . _
fty 6,'1999- i
.. Mr. JImes W. Langenbach, Vice Pr:sidInt -
~
1 cnd Director- TMI - <
r GPU Nuclear, Inc.
Middletown, PA' 17057_ ,
j
SUBJECT:
TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) 279-CORE L PROTECTION SAFETY LIMIT REQUEST FOR ADDITIONAL INFORMATION FOR THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1(TAC NO. MA4301).
Dear Mr. Langenbach:
The NRC staff has reviewed your application dated December 3,1998, as supplemented by letters dated March 26 and April 16,1999, which requested review and approval of a revised core protection safety limit and bases for TMl-1 to reflect an average of 20 percent of tubes ]
plugged per steam generator. The staff has determined it will need the additional information I identified in the enclosure in order to complete its review. In order for the staff to support your requested review completion schedule, please provide the requested information within 10 days of receipt of this letter. The information in the enclosure and this request have been previously discussed with Mr. D. Distel of GPU Nuclear, Inc., and a copy of this letter is being faxed to Mr. Distel.
This is the staff's second formal request for additional information on TSCR 279. If you have any questions, please contact me at (301) 415-1402.
Sincerely, ORIGINAL SIGNED BY:
Timothy G. Colbum, Sr. Project Manager, Section 2 Project Directorate l Division of Licensing Project Management ,
Office of Nuclear Reactor Regulation Docket No. 50-289
~
Enclosure:
Request for Additionalinformation cc w/ encl: See next page
. DISTRIBUTION: f1 EDeshet Filei TClark JZwolinski/SBlack TColburn JTatum / 'i PUBLIC PDI R/F OGC ACRS PEselgroth, RI MShuaibi GHubbard JHannon DDiec h
l 9905110182 990506 PDR P ADOCK 05000289 PDR 10022 DOCUMENT NAME: G:\CdL8 URN \4301RAl2.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure /"N" = No copy lE LA:PD1 M 0FFICE PM:PD1 ^. lN SC:PQj/ l SPLB , , 7 NAME IColburn ' ' TClark d\/ J_CliMord GHubbard M DATE 3/6 /99 6 / 16 /99 4/ ( a /99 f// /99 Official Record Copy .
j
~
y ,
1 5"c
, og y
' .) .. . 4 UNITED STATES '
'g g . NUCLEAR REGULATORY COMMISSION
'f- WASHINGTON, D.C. 20555-0001
,,,,, . May 6, 1999 Mr. James W. Langenbach, Vice President
. and Director - TMI GPU Nuclear, Inc.
P. O. Box 480 Middletown, PA 17057
SUBJECT:
TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) 279-CORE PROTECTION SAFETY LIMIT REQUEST FOR ADDITIONAL INFORMATION i FOR THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TAC NO. MA4301)
Dear Mr. Langenbach:
\
The NRC staff has reviewed your application dated December 3,1998, as supplemented by
-letters dated March 26 and April 16,1999, which requested review and approval of a revised core protection safety limit and bases for TMI-1 to reflect an average of 20 percent of tubes plugged per steam generator. The staff has determined it will need the additional information identified in the enclosure in order to complete its review, in order for the staff to support your ;
requested review completion schedule, please provide the requested information within 10 days j of receipt of this letter, The information in the enclosure and this request have been previously discussed with Mr. D. Distel of GPU Nuclear, Inc., and a copy of this letter is being faxed to Mr.
Distel. H This is the staff's second formal request for additional information on TSCR 279, if you have any questions, please contact me at (301) 415-1402. l Sincerely, d '
Timothy G. Colburn, Sr. Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Request for Additional
. information cc w/ encl:: See next page
..,.m.r s.
F-
.o.
+.-
Three Mile Island Nuclear Station, Unit No.1.
cc:
l Michael Ross
' Director, O&M, TMl Robert B. Borsum ,
GPU Nuclear, Inc.
. P.O. Box 480 B&W Nuclear Technologies )
Suite 525 Middletown, PA 17057 1700 Rockville Pike
. Rockville, MD 20852 John C. Fomicola .
Director, Planning and William Domsife, Acting Director Regulatory Affairs Bureau of Radiation Protection GPU Nuclear, Inc. Pennsylvania Department of 100 Interpace Parkway Environmental Resources l Parsippany, NJ 07054 P.O. Box 2063 '
Harrisburg, PA 17120 Jack S. Wetmore Manager, TMI Regulatory Affairs Dr. Judith Johnsrud i GPU Nuclear, Inc. National Energy Committee P.O. Box 480 Sierra Club Middletown, PA 17057 433 Orlando Avenue State College, PA 16803 Emest L. Blake, Jr., Esquire _ i Shaw, Pittman, Potts & Trowbridge Peter W. Eselgroth, Region 1 2300 N Street, NW. U.S. Nuclear Regulatory Commission Washington, DC 20037 475 Allendale Road King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120
' Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (TMI-1)
U.S. Nuclear Regulatory Commission
' P.O. Box 219 Middletown, PA 17057 Regional Administrator I Region i .
U.S. Nuclear Regulatory Commission
. 475 Allendale Road King of Prussia, PA 19406 l
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t Reauest for Additional information Technical Specification Chance Reauest (TSCR) 279 Core Protection Safety Limits
- 1. Define specifically with respect to TSCR 279 what the total EFW (emergency feedwater) flow requirement is, assuming 20 percent average tubes plugged in the once through steam generators, including the flow breakdown, i.e., how much flow is necessary for decay heat -
removal, pump recirculation, bearing cooling, instrument inaccuracy, etc. and describe how the i flow balance will be assured and maintained over time.
- 2. Assuming maximum allowed pump degradation (for all three EFW pumps) as permitted by the ASME Code, compare the established EFW flow requirement above with the EFW flow that will be delivered assuming the worst-case pump combination (assuming single failure).
- 3. In responding to question 1 of the NRC's letter dated March 10,1999, regarding TMI-1
! TSCR 279, you discussed the loss of feedwater accident and stated in a letter dated March 26, L .1999, that the EFW system was conservatively assumed to deliver flow (550 gpm) to the steam i generators starting 43 seconds after the initiation signal with any (emphasis added) l combination of EFW pumps (1 TDP or 2 MDPs or 1 TDP and 1 MDP). However, the information you provided during the April 23,1999, meeting with the staff indicated that the maximum predicted flow capability of the TDP is 536 gpm. Please either confirm the capability of the TDP to deliver the required 550 gpm flow, or amend your response to question 1 to clarify the correct combination of pumps necessary to achieve the required 550 gpm flow.
This information is necessary for the staff to accurately understand and evaluate the TMi-1
- EFW pump capability as it applies to the flow requirement of 550 gpm total flow to the once L through steam generators as stated in your March 26,1999, letter, i
L Enclosure
