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Category:BOARD NOTIFICATION (TO LICENSING BOARD OR LICENSING
MONTHYEARML20207L8991986-12-23023 December 1986 Board Notification 86-025:forwards Safety Evaluation Rejecting Util Fracture Mechanics Methodology Used to Justify Tech Spec Change Request 148 Re Plugging Limits for once-through Steam Generator Tubes ML20141N5691986-02-21021 February 1986 Board Notification 86-006:forwards Proposed Notice of Consideration of Issuance of Amend to License DPR-50 & Proposed NSHC Determination & Opportunity for Hearing Re 860204 Request to Modify Steam Generator Repair Criteria ML20128E1951985-05-28028 May 1985 Board Notification 85-059:forwards Financial Review of Gpu Operation of TMI-1.Util Has Reasonable Assurance of Obtaining Funds Necessary to Cover Estimated TMI-1 Operating Costs for Period of Licensing & Decommissioning ML20127D7251985-05-14014 May 1985 Board Notification 85-054:forwards Exam Repts 50-289/84-32 & 50-289/84-09 Re Operator Licensing Exams.Repts Indicate That Candidates Well Prepared for Written & Operational Exams ML20133P9301985-04-0202 April 1985 Board Notification 85-033:informs That in Order to Avoid Potential Limitations on Plant Readiness for Restart,Util Will Proceed to Plug All Tubes W/Eddy Current Indications Exceeding Tech Spec Plugging Limit ML20127B0801983-11-23023 November 1983 Board Notification 83-184:provides Addl Info on Steam Generator Repair Program & Requests Concurrence on Final No Significant Hazards Determination Re Operation W/Repaired Generators.Commission Papers Encl ML20151H4871983-05-0404 May 1983 Board Notification 83-057:forwards Differing Prof Opinions Re Sys Interaction & Safety Classification.Info Relates to Board Notifications 83-17 & 83-44 Re Unresolved Safety Issue A-17 ML20204F0461983-04-12012 April 1983 Board Notification 83-42:forwards Info Re Unanalyzed Reactor Vessel Thermal Stress During Cooldown.B&W Informed NRC of Preliminary Safety Concern Evolving from Further Consideration of 800610 St Lucie Upper Head Voiding Event ML20204F0361983-03-0404 March 1983 Board Notification 83-27:forwards 830221 Memo & Final Eg&G Rept Re Addl RELAP-5 Calculation for Semiscale S-SR-2 Test ML20062E1651982-07-27027 July 1982 Board Notification 82-71:informs That NRC Did Not Rely on Feed & Bleed Cooling to Protect Core & Forwards Info Supporting Info ML20058A8101982-07-0909 July 1982 Board Notification 82-65:forwarding New Info Re NRC Analysis of post-accident/long-term Cooling Following Small Breaks in Primary Sys.Draft Lasl Rept, Small Break LOCA Recovery in B&W Plants Encl 1986-02-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months 1999-09-29
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UNITED STATES s p,
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-l NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 k *****
./ April 2, 1985 Docket No. 50-289 MEMORANDUM FOR: Chairman Palladino Commissioner Roberts Commissioner Asselstine Commissioner Bernthal Commissioner Zech FROM:
Hugh L. Thompson, Jr. , Director Division of Licensing, NRR
SUBJECT:
BOARD NOTIFICATION (BN 033 )
RECENT DEVELOPMENTS RELATED TO TMI-1 STEAM GENERA This Notification is being provided to the Comission in accordance with the revised Commission's notification policy of July 6,1984, to inform the Commission may on all issues involve substantial on the public, press, or cases beforeinterest.
Congressional the Comission or issues w With reference letter dated Merchto BN-85-028 dated March 15, 1985, the licensee informed us by 29, 1985 (enclosed), that in order to avoid any potential limitations on plant readiness for restart it will proceed to plug all tubes with eddy current indications exceeding the present Technical Specification plugging limit depth of 40% through wall. This repair is scheduled to be completed before the middle of April.
The licensee requested that we continue our review of their request to revise the plugging limit with regard to any future defects.
kk'f '
. Jr fughL7 Thomson,Jr., Director N
Division of Licensing, NRR
Enclosure:
As Stated cc w/ enclosure:
See next page 8508140537 850402 PDR ADOCK 05000289 P PDR
i-
-?-
cc.w/ enclosure:
Judge Sheldon J. Wolfe, ASLB Judge Gustava A. Linenberger, Jr., ASLB
- Judge Ivan W. Smith, ASLB Judge Reginald L. Gotchy, ASLAB Judge Christine N. Kohl, ASLAB Judge Gary L. Edles, ASLAB Parties to Hearing
- OPE -
'0GC EDO' SECY-2 ACRS-10-~
& 55 15:34 l G"U IU2.EM CCR" NO.017 002 e
BG NuoBesr 2"n:: =;"'
Fa's peary.Nea .'en ,v C7 (20 0 2S3-6500 TELEX 136 432
. Wrder's Dife:I 0:a' Nurr.ce' March 29,1985 5211-85-2057 Office of Nuclear Reactor Regulation Attn: J.F.Stolz, Chief ,
Operating Reactor Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station Unit 1 (T111-1)
Operating License No. DPR 50 Docket No. 50-E8g Steam Generator Repair Limits By letters dated Januery 31 and March 1,1985, GPU Nuclear Corporation requested approval of revised repair criteria, i.e., plugging linits, for the steam generator tubes. As documented in those letters, this approach is technically sound and does not constitute an unreviewed safety question. We have reached the point, however, where we must act now to avoid any potential limitations on TMI-1 plant readiness for restart. Accordingly, I have determinea to proceed immediately to plug the steam generator tubes in accordance with the existing repair limits specified in Technical Specification paragraph 4.19.4.a.6. cf the cperating license.
We ask that the staff continue its technical review of cur regest so as to help us avoid unnecessary plugging in the future.
! We will advise you when the plugging has been ccmpleted.
Very truly yours, 3 P.R. Clark President PRC/mak f[2 b GPU Nuc! ear Co ;staten :s a s'.:sd ary Of Ga .eralPt.c' C Utd t es Corcerat on