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| | issue date = 06/19/1986 | | | issue date = 06/19/1986 |
| | title = Requests Permission to Apply Code Case N-411 Re Spectral Damping Values Used in Piping Stress Analysis Instead of Section Iii,Div I,Table N-1230-1 Values.Fee Paid | | | title = Requests Permission to Apply Code Case N-411 Re Spectral Damping Values Used in Piping Stress Analysis Instead of Section Iii,Div I,Table N-1230-1 Values.Fee Paid |
| | author name = WOODY C O | | | author name = Woody C |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = DENTON H R | | | addressee name = Denton H |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000000, 05000250, 05000251, 05000335, 05000389 | | | docket = 05000000, 05000250, 05000251, 05000335, 05000389 |
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| {{#Wiki_filter:ACCESS/QN NBR: FAC IL: 50-000 50-250 50-251 50-335 5O-389 AUTH.NAl'tE WOODY'.Q.REC IP.NAME DENTQNi H.R.REGULATOR INFORMATION DISTRIBUTION STEM (R XDS>8606240371 DOC.DATE: 86/06/19 NOTARIZED: | | {{#Wiki_filter:REGULATOR INFORMATION DISTRIBUTION STEM (R XDS> |
| NO DOCKET 4: Genev ic Docket 05000000 Turkey Point Planti Unit 3i Flov ida Poroer and Ligh+C 05000250 Turkey Point Plant.Unit 4i Florida Pa>ocr and Ligh+C 05000251 St.Lucie Planti Unit li Flov ida Power Zc Light Co.05000335 St.Lucie Planti Unit 2i Flov ida Power 8c Light Co 05000389 AUTHOR AFFXLI AT I ON Florida.Power~c Light Co.RECIPIENT AFFILIATION Office of Nuclear Reactov Regulation. | | ACCESS/QN NBR: 8606240371 DOC. DATE: 86/06/19 NOTARIZED: NO DOCKET 4: |
| Direc tov (post 851125 | | FAC IL: 50-000 Genev ic Docket 05000000 50-250 Turkey Point Planti Unit 3i Flov ida Poroer and Ligh+ C 05000250 50-251 Turkey Point Plant. Unit 4i Florida Pa>ocr and Ligh+ C 05000251 50-335 St. Lucie Planti Unit li Flov ida Power Zc Light Co. 05000335 5O-389 St. Lucie Planti Unit 2i Flov ida Power 8c Light Co 05000389 AUTH. NAl'tE AUTHOR AFFXLIATI ON WOODY'. Q. Florida. Power ~c Light Co. |
| | REC IP. NAME RECIPIENT AFFILIATION DENTQNi H. R. Office of Nuclear Reactov Regulation. Direc tov (post 851125 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Requests pev mission to apply Code Case N-411 v e spectral damping values used in piping stress analysis instead of Section Ill>Div I>Table N-1230-1 values.Fee paid.DISTRIBUTION CODE'001D COPXES RECEIVED: LTR i ENCL'IZE: TITLE: QR Submittal: | | Requests pev mission to apply Code Case N-411 v e spectral damping values used in piping stress analysis instead of Section Ill> Div I> Table N-1230-1 values. Fee paid. |
| General Distribution NOTES: RECXP IENT ID CODE/NANE pNR-A EB PWR-A EICSB PNR-A FOB PWR-A PD2 LA PNR-A PD2 PD 01 licDONALD, D pNR-*PSB PNR-A RSB INTERNAL: ADN/LFNB ELD/HDS2 NRR/GRAS RGN2 COPIES LTTR ENCL 1 1 2 2 1 1 1 0 5 5 1 1 1 1 0 1 0 0 1 RECIPXENT ID CODE/NANE PWR-B EB PNR-B PEICSB PWR-B FOB PWR-B PD8 LA PWR-B PD8 PD 01 TOURIGNY>E PNR-B PEICSB PNR-B RSB ELD/HDSO N/HFT/TSCB REG FIL 04 COP IES LTTR ENCL 1 2 0 5 5 1 1 0 1 1 EXTERNAL: EGZcG BRUSQUE>S NRC PDR 02 1 1 1 1 LPDR NSIC 03.2 2 05 1 1 TOTAL NUl']HER OF COPIES REQUIRED: LTTR 38 ENCL 32 IM)MJ'Il I fl'II*;I I M I I r MM fl"-'i fiff, f I I~f I M'I I P,M If J fl)P I"I Iif I.Mq I M'I I Mi il,>>'-1" 3" f II C'I I, M M-]'3',.lP/f lI I fi 0 i'+i 87>FLORIDA POWER&LIGHT COMPANY JQQ 1 9198B L-86-209 Mr.Harold R: Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | DISTRIBUTION CODE'001D COPXES RECEIVED: LTR i ENCL'IZE: |
| | TITLE: QR Submittal: General Distribution NOTES: |
| | RECXP IENT COPIES RECIPXENT COP IES ID CODE/NANE LTTR ENCL ID CODE/NANE LTTR ENCL pNR-A EB 1 1 PWR-B EB 1 PWR-A EICSB 2 2 PNR-B PEICSB 2 PNR-A FOB 1 1 PWR-B FOB PWR-A PD2 LA 1 0 PWR-B PD8 LA 0 PNR-A PD2 PD 01 5 5 PWR-B PD8 PD 01 5 5 licDONALD, D 1 TOURIGNY> E pNR-* PSB 1 PNR-B PEICSB PNR-A RSB 1 PNR-B RSB 1 INTERNAL: ADN/LFNB 1 0 ELD/HDSO 1 0 ELD/HDS2 1 0 N / HFT/TSCB 1 NRR/GRAS 0 REG FIL 04 1 RGN2 1 EXTERNAL: EGZcG BRUSQUE> S 1 1 LPDR 03 .2 2 NRC PDR 02 1 1 NSIC 05 1 1 TOTAL NUl']HER OF COPIES REQUIRED: LTTR 38 ENCL 32 |
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| ==Dear Mr.Denton:==
| | IM |
| RE: St.Lucie Units 1 and 2 Docket Nos.50-335 and 50-389 Turkey Point Units 3 and 0 Docket Nos.50-250 and 50-251 Re uest for ASME Code Case N-Oil"A royal 1 Reference Documents:
| | )MJ Il I |
| 1.NUREG-1061, Volume 2,"Report of the U.S.Nuclear Regulatory Commission Piping Review Committee, Evaluation of'Seismic Designs-A Review of Seismic Design.Requirements for Nuclear Power Piping." 2.L'etter from Thomas M.Novak (NRC)to D.W.Mazur (Washington Public Power Supply System), Docket No.50-060, WNP-I,"Approval of ASME Code Case N-Ol l." In accordance with Article NCA-1100 of the ASME Section III Code, Florida Power R Light Company (FPL)requests Commission approval to apply Code Case N-Ol 1 as described below.Code Case N-011 (copy attached)provides spectral damping values which may be used in lieu of Section III, Division I, Table N-1230-1 values.The original Section III values for spectral damping are identical to those considered acceptable to the Commission in Regulatory Guide 1.61.The N-Ol I damping values are endorsed by Reference I, which recommends that Regulatory Guide 1.61 be revised to incorporate the new criteria.FPL would utilize the new criteria on the St.Lucie and Turkey Point projects as follows: 1.Upon receipt of, Commission approval to utilize the subject Code Case, FPL would authorize the development of new response spectra curves which would reflect the application of the Pressure Vessel Research Committee (PVRC)criteria.Existing response spectra would be retained as Quality Assurance records however, since all existing piping'stress analysis calculations of record make reference to them.Ll:1 860$24037i g00250 PDR ADo PDR p/PEOPLE ,.SERVING PEOPLE I 8~
| | II fl |
| Mr.Harold R.Denton, Director L-86-249 Page two 2.'PL is presently engaged in a study to assess the cost feasibility of implementing a comprehensive support optimization (i.e., snubber reduction) program for the St.Lucie project.Should the study yield positive results regarding the cost effectiveness of such an undertaking, FPL may, at our option, utilize the PVRC damping values as the principal tool toward optimizing supports through reanalysis.
| | *;I I M I |
| Depending on the outcome of the St.Lucie effort, a similar snubber reduction effort may be undertaken for Turkey Point Units 3 and 4.3.Until support optimization efforts commence at any of the nuclear units, FPL may use the new PVRC damped response spectra on an interim basis to qualify anomalous piping conditions (such as may be discovered during inservice inspections) to avoid costly corrective actions such as physical modifications to piping or supports.4.Code Case N-4I I may, at FPL's option, be applied to new systems analyzed by response spectrum methods.Code Case N-4I I may also be utilized to qualify proposed modifications to~existin systems.Based on the use of Code Case N-4I I, all piping qualification analyses would continue to include, but not be limited to, verification that: All affected piping supports are properly designed and capable of withstanding revised design loads.Excessive pipe deflections are not introduced when supports are optimized (i.e., displacements would be checked to verify that proper clearances exist with respect to adjacent=structures, components and equipment).
| | r MM fl " -'i I |
| Pipe mounted equipment would also be checked to assure that the equipment could withstand the increased pipe motion.r Postulated pipe break locations have been properly considered. | | fiff, fI I I 'I |
| 'ffected equipment nozzle loads are not adversely affected.Each new analysis or reanalysis performed utilizing the PVRC damping values will include specific reference to Code Case N-4I I in the Quality Assurance Records associated with the calculation.
| | ~ f M I |
| For each anchor group (analysis package)where the code case is applied, the code case would be applied to the entire analysis (i.e., PVRC damping would not be mixed in a given analysis with Regulatory Guide l.6 I criteria). | | If P,M J fl)P I "I Iif I. |
| Code Case N-4I I will be applied to systems analyzed by response spectrum methods, but not to those using time-history analysis methods.MAS3/00 I/2 Mr.Harold R.Denton, Director L-86-249 Page three The mechanism for implementing the new criteria will be to document Commission approval to utilize Code Case N-4I I in a future amendment to the affected Final Safety Analysis Reports.Additionally, FPL would instruct its contractors performing piping stress analysis calculations to revise affected Quality Assurance Program procedures. | | IMq M I |
| Please note that permission to utilize Code Case N-4I I damping values has already been granted to another nuclear project (see Reference 2).To support existing schedules for initiating support optimization efforts, FPL would appreciate receiving Commission approval to apply Code Case N-4I I criteria to St.Lucie Units I and 2 and Turkey Point Units 3 and 4 by August I5, l 986.FPL Check No.I366 is attached in accordance with the fee schedule specified in IO CFR l70.2 I.Very truly yours, C.O.Wood Group Vic resident Nuclear Energy COW/MAS/gp Attachments cc: Ashok C.Thadani, Director, PWR Project Directorate II8 Lester S.Rubenstein, Director, PWR Project Directorate II2 Dr.J.Nelson Grace, USNRC, Region II Harold F.Reis, Esquire, Newman&Holtzinger MAS3/00 I/3 CASES OF ASME BOILER AND PRESSURE VESSEL CODE CA5R N-411-1 Approval Date: February 20, 1986 See Numerical Index for expfratfon and any reafffrmarfon darer.Case N411-1 Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping Section I I I, Division 1 Inquiry: What alternatives to the damping values given in Section III, Division 1, Table N-1230-1 are acceptable for use in response spectra analysis of Class 1, 2, and 3 piping?Reply: It is the opinion of the Committee that for Section III, Division 1, Class 1, 2, and 3 construction, the damping value for response spectra analysis of piping shown in Fig.1 may be used as an alternative to those given in Table N-1230.1.The damping value in Fig.1 is applicable to both Operating Basis Earthquakes and Safe Shutdown Earth-quakes a'nd is independent of pipe diameter.The damping value in Fig.1 is also applicable to other response spectra-type dynamic loads for which the response spectra is generated after being filtered through the building structure. | | 'I Mi II il,>> |
| Damping values to be used with spectra with responses above 33 Hs shall be evaluated and designated by the designer.This Case number shall be shown in the documenta. | | '-1" 3" f C'I I, M |
| tion for this analysis and on the Code Data Report." 3 as C CL 2 E O I I I I I I 1 I I I 0 0 10 20 Frequency, Hz FIG.1 DAMPING VALUES FOR RESPONSE.SPECTRA ANALYSIS OF PIPING 33 817 SUPP.13-NC}} | | M- |
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| | 0 i'+i 87> |
| | FLORIDA POWER & LIGHT COMPANY JQQ 1 9198B L-86-209 Mr. Harold R: Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
| | |
| | ==Dear Mr. Denton:== |
| | |
| | RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Turkey Point Units 3 and 0 Docket Nos. 50-250 and 50-251 1 |
| | Re uest for ASME Code Case N-Oil "A royal Reference Documents: |
| | : 1. NUREG-1061, Volume 2, "Report of the U. S. Nuclear Regulatory Commission Piping Review Committee, Evaluation of'Seismic Designs-A Review of Seismic Design. Requirements for Nuclear Power Piping." |
| | : 2. L'etter from Thomas M. Novak (NRC) to D. W. Mazur (Washington Public Power Supply System), Docket No. 50-060, WNP-I, "Approval of ASME Code Case N-Ol l." |
| | In accordance with Article NCA-1100 of the ASME Section III Code, Florida Power R Light Company (FPL) requests Commission approval to apply Code Case N-Ol 1 as described below. |
| | Code Case N-011 (copy attached) provides spectral damping values which may be used in lieu of Section III, Division I, Table N-1230-1 values. The original Section III values for spectral damping are identical to those considered acceptable to the Commission in Regulatory Guide 1.61. The N-Ol I damping values are endorsed by Reference I, which recommends that Regulatory Guide 1.61 be revised to incorporate the new criteria. FPL would utilize the new criteria on the St. Lucie and Turkey Point projects as follows: |
| | : 1. Upon receipt of, Commission approval to utilize the subject Code Case, FPL would authorize the development of new response spectra curves which would reflect the application of the Pressure Vessel Research Committee (PVRC) criteria. Existing response spectra would be retained as Quality Assurance records however, since all existing piping 'stress analysis calculations of record make reference to them. |
| | 860$ 24037i g00250 PDR ADo PDR Ll:1 p / |
| | PEOPLE ,.SERVING PEOPLE |
| | |
| | I 8 ~ |
| | |
| | Mr. Harold R. Denton, Director L-86-249 Page two 2.'PL is presently engaged in a study to assess the cost feasibility of implementing a comprehensive support optimization (i.e., snubber reduction) program for the St. Lucie project. Should the study yield positive results regarding the cost effectiveness of such an undertaking, FPL may, at our option, utilize the PVRC damping values as the principal tool toward optimizing supports through reanalysis. |
| | Depending on the outcome of the St. Lucie effort, a similar snubber reduction effort may be undertaken for Turkey Point Units 3 and 4. |
| | : 3. Until support optimization efforts commence at any of the nuclear units, FPL may use the new PVRC damped response spectra on an interim basis to qualify anomalous piping conditions (such as may be discovered during inservice inspections) to avoid costly corrective actions such as physical modifications to piping or supports. |
| | : 4. Code Case N-4I I may, at FPL's option, be applied to new systems analyzed by response spectrum methods. Code Case N-4I I may also be utilized to qualify proposed modifications to~existin systems. |
| | Based on the use of Code Case N-4I I, all piping qualification analyses would continue to include, but not be limited to, verification that: |
| | All affected piping supports are properly designed and capable of withstanding revised design loads. |
| | Excessive pipe deflections are not introduced when supports are optimized (i.e., displacements would be checked to verify that proper clearances exist with respect to adjacent= structures, components and equipment). Pipe mounted equipment would also be checked to assure that the equipment could withstand the increased pipe motion. |
| | r Postulated pipe break locations have been properly considered. |
| | equipment nozzle loads are not adversely affected. 'ffected Each new analysis or reanalysis performed utilizing the PVRC damping values will include specific reference to Code Case N-4I I in the Quality Assurance Records associated with the calculation. For each anchor group (analysis package) where the code case is applied, the code case would be applied to the entire analysis (i.e., PVRC damping would not be mixed in a given analysis with Regulatory Guide l.6 I criteria). |
| | Code Case N-4I I will be applied to systems analyzed by response spectrum methods, but not to those using time-history analysis methods. |
| | MAS3/00 I /2 |
| | |
| | Mr. Harold R. Denton, Director L-86-249 Page three The mechanism for implementing the new criteria will be to document Commission approval to utilize Code Case N-4I I in a future amendment to the affected Final Safety Analysis Reports. Additionally, FPL would instruct its contractors performing piping stress analysis calculations to revise affected Quality Assurance Program procedures. |
| | Please note that permission to utilize Code Case N-4I I damping values has already been granted to another nuclear project (see Reference 2). To support existing schedules for initiating support optimization efforts, FPL would appreciate receiving Commission approval to apply Code Case N-4I I criteria to St. Lucie Units I and 2 and Turkey Point Units 3 and 4 by August I5, l 986. |
| | FPL Check No. I366 is attached in accordance with the fee schedule specified in IO CFR l70.2 I. |
| | Very truly yours, C. O. Wood Group Vic resident Nuclear Energy COW/MAS/gp Attachments cc: Ashok C. Thadani, Director, PWR Project Directorate II8 Lester S. Rubenstein, Director, PWR Project Directorate II2 Dr. J. Nelson Grace, USNRC, Region II Harold F. Reis, Esquire, Newman & Holtzinger MAS3/00 I /3 |
| | |
| | CA5R N-411-1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: February 20, 1986 See Numerical Index for expfratfon and any reafffrmarfon darer. |
| | Case N411-1 Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping Section I I I, Division 1 Inquiry: What alternatives to the damping values given in Section III, Division 1, Table N-1230-1 are acceptable for use in response spectra analysis of Class 1, 2, and 3 piping? |
| | 3 Reply: It is the opinion of the Committee that for as I I |
| | Section III, Division 1, Class 1, 2, and 3 construction, C 2 I the damping value for response spectra analysis of piping CL E I shown in Fig. 1 may be used as an alternative to those O I |
| | I given in Table N-1230.1. 1 I |
| | The damping value in Fig. 1 is applicable to both I I |
| | Operating Basis Earthquakes and Safe Shutdown Earth-0 quakes a'nd is independent of pipe diameter. 0 10 20 33 The damping value in Fig. 1 is also applicable to other Frequency, Hz response spectra-type dynamic loads for which the response spectra is generated after being filtered through the building structure. FIG. 1 DAMPING VALUES FOR RESPONSE Damping values to be used with spectra with responses .SPECTRA ANALYSIS OF PIPING above 33 Hs shall be evaluated and designated by the designer. |
| | This Case number shall be shown in the documenta. |
| | tion for this analysis and on the Code Data Report. |
| | 817 SUPP. 13- NC}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML20217F6171999-10-0808 October 1999 Forwards Insp Repts 50-335/99-11 & 50-389/99-11 on 990827 & 990907-09.No Violations Identified.Matl Encl Contained Safeguards Info as Defined by 10CFR73.21 & Disclosed to Unauthorized Individuals Prohibited by Section 147 of AEA ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML20209F1541999-07-0606 July 1999 Informs That NRC in Process of Conducting Operational Safeguards Response Evaluations at Nuclear Power Reactors. Plant Chosen for Such Review Scheduled for Wk of 990823-26 ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 ML20195F3871999-06-11011 June 1999 Final Response to FOIA Request for Documents.App a Records Being Withheld in Entirety (Ref FOIA Exemption 5) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17241A5001999-10-21021 October 1999 Forwards Rev 3 to Emergency Response Data Sys (ERDS) Data Point Library for St Lucie Unit 1.Rev Provides Replacement Pages & Follows Format Recommended by NUREG 1394, ERDS Implementation, Rev 1,App C ML17309A9981999-10-19019 October 1999 Forwards Revised Epips,Including Rev 3 to EPIP-10 & Rev 25 to HP-202.EPIP-10 Added Onsite Monitoring Points,Made Administrative Changes & Incorporated New Attachments & HP-202 Added Red Team Survey Points ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17241A4811999-10-0101 October 1999 Reports Number of Tubes Plugged During Unit 1 Refueling Outage SL1-16,per TS 4.4.5.5.a ML17241A4701999-09-25025 September 1999 Forwards Info Requested by NRC Staff During 990916 Telcon to Complete Staff Review of Request for risk-informed Extension of Action Completion/Aot Specified for Inoperable Train of LPSI Sys at Plant ML17241A4721999-09-24024 September 1999 Forwards Rev 1 to Plant Change/Mod (PCM) 99016 to St Lucie Unit 1,Cycle 16 COLR, IAW TS 6.9.1.11.d.Refueling Overhaul Activities Are Currently in Progress & Reactor Operations for Cycle 16 Are Scheduled to Commence in Oct 1999 ML17241A4681999-09-22022 September 1999 Requests Restriction Be Added to Senior Operator License SOP-21093 for TE Bolander.Nrc Forms 369,encl.Encl Withheld Per 10CFR2.790(a)(6) ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17241A4671999-09-20020 September 1999 Forwards Completed NRC Form 536, Operator Licensing Exam Data, for St Lucie Units 1 & 2,as Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. ML17241A4581999-09-13013 September 1999 Forwards Info Requested by NRC Staff During 990630 & 0816 Telcons,To Complete Review of Proposed License Amend for Fuel Reload Process Improvement Program ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17241A4521999-08-31031 August 1999 Withdraws Relief Request 16 & Suppl Relief Request 15 with Info Requested During 990526 Telephone Conference Re ISI Insp Plan,Third 10-yr Interval ML17241A4531999-08-31031 August 1999 Informs That No Candidates from St Lucie Plant Will Be Participating in PWR Gfes Being Administered on 991006 ML17241A4501999-08-26026 August 1999 Informs That FPL Has Reviewed Reactor Vessel Integrity Database,Called RVID2,re Closure of GL 92-01,rev 1,suppl 1. Requested Corrections & Marked Up Pages from Rvid 2 Database Summary Repts That Correspond to Comments,Attached ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17241A4371999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data for six- Month Period Ending 990630,per 10CFR26.71(d) ML17241A4461999-08-11011 August 1999 Requests That W Rept Entitled, Evaluation of Turbine Missile Ejection Probability Resulting from Extending Test Interval of Interceptor & Reheat Stop Valves at St Lucie Units 1 & 2, Be Withheld from Public Disclosure L-99-171, Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3)1999-07-29029 July 1999 Forwards Rev 56 to Physical Security Plan.Summary of Changes & Marked Up Copy of Revised Pages Also Encl.Encls Withheld from Public Disclosure Per 10CFR2.790(a)(3) ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17309A9911999-07-26026 July 1999 Forwards Revised EPIPs & Revised Procedures That Implement Emergency Plan as Listed.Procedures Provides Instruction for Operational Support Ctr (OSC) Chemistry Supervisor to Establish Remote Labs at Locations Specified ML17241A4151999-07-22022 July 1999 Forwards Revised Relief Request 25 for Second 10-yr ISI Interval for Unit 2 ML17241A4221999-07-22022 July 1999 Forwards List of Proposed Licensing Actions for St Lucie Units 1 & 2,planned During Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. ML17241A4471999-07-22022 July 1999 Requests That Rev 1 to WCAP-14732 & Rev 1,Add 1 to WCAP-14732 Be Withheld from Public Disclosure ML17241A4101999-07-16016 July 1999 Forwards FP&L Supplemental Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17309A9881999-07-0707 July 1999 Forwards Rev 5 to EPIP-03, Emergency Response Organization Notification/Staff Augmentation. Rev 5 to EPIP-03 Was Revised to Transfer EP Responsibilities from Training Manager to Protection Svcs Manager ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17241A3971999-06-30030 June 1999 Forwards Suppl Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, as Requested in 990317 Ltr ML17241A4011999-06-30030 June 1999 Forwards Info Copy of Florida Wastewater Permit (FL0002208) (Formerly NPDES Permit) Mod,Which Was Issued by Florida Dept of Environ Protection on 990604 ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17241A3951999-06-29029 June 1999 Provides Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants, Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17241A3731999-06-17017 June 1999 Supplements Relief Requests 4,11 & 13 for Third ten-year ISI Interval with Info Requested During 990526 Telcon.Expedited Review Is Requested by 990730 to Avoid Negatively Impacting Upcoming St Lucie Unit 1 Refueling Outage (SL1-16) ML17241A3641999-06-14014 June 1999 Submits Supplement to Relief Request 24 with Info Requested by Nrc.In Addition Relief Request 24 Is Identical to St Lucie Unit 1 Relief Request 4 for Third ISI Interval Being Supplemented by FPL Ltr L-99-139 L-99-129, Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3)1999-06-0909 June 1999 Forwards Rev 55 to Physical Security Plan,Summary of Changes & Marked Up Copy of Revised Pages.With Directions for Incorporating Rev Into Plan & Copies of Replacement Pages.Rev Withheld,Per 10CFR2.790(a)(3) ML17241A3601999-06-0707 June 1999 Forwards Correction to Annual Radiological Environ Operating Rept for CY98.Util Has Identified Transcription Error on Last Page of Attachment C of Rept,Results from Interlaboratory Comparison Program 1998 ML17241A3561999-06-0707 June 1999 Forwards Rept Containing Brief Description & Summary of SEs for Changes,Tests & Experiments Which Were Approved for Unit 3 During Period of 970526-981209 ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. ML17223A9401990-09-13013 September 1990 Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility ML17223A9341990-09-10010 September 1990 Forwards Addl Info Re Generic Implications & Resolution of Control Element Assembly (CEA) Failure at Facility,Per NRC Request.Description of Testing Program for Old Style CEAs in Unit 1 Core Encl ML17348A5501990-09-0707 September 1990 Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities ML17348A5461990-09-0707 September 1990 Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval. ML17348A5521990-09-0606 September 1990 Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs ML17348A5431990-08-31031 August 1990 Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA L-90-315, Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 81990-08-30030 August 1990 Advises That Util Has Completed Evaluation of NUREG-0737, Item II.D.1,SER Item 8 ML17223A9201990-08-28028 August 1990 Forwards Forms NIS-1 & NIS-2, Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules, Per 900725 Ltr ML17348A5361990-08-27027 August 1990 Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners. ML17348A5171990-08-24024 August 1990 Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request ML17223A8911990-08-20020 August 1990 Forwards Corrected Monthly Operating Repts for Jul 1990 for St Lucie Units 1 & 2 & Summary of Operating Experience ML17348A5041990-08-17017 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 L-90-301, Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant1990-08-16016 August 1990 Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant ML17348A5051990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3 ML20059B0111990-08-14014 August 1990 Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813 ML17348A4971990-08-10010 August 1990 Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed IR 05000335/19900141990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor ML17223A8751990-08-0909 August 1990 Responds to Violations Noted in Insp Rept 50-335/90-14. Corrective Actions:Rcs Flow Determination by Calorimetric Procedure Repeated W/Supervisor of Individual Observing & Individual Counseled by Supervisor ML17348A4701990-07-27027 July 1990 Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing ML17348A4281990-07-25025 July 1990 Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b) ML17223A8621990-07-25025 July 1990 Advises That NIS-1 & NIS-2 Forms,As Part of Inservice Insp Rept,Will Be Submitted by 900831 ML17223A8631990-07-25025 July 1990 Submits Addl Info Re Implementation of Programmed Enhancements Per Generic Ltr 88-17, Loss of Dhr. All Mods for Unit 1 Completed & Operational.Mods for Unit 2 Schedule for Upcoming Refueling Outage L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990 Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790) ML17348A4691990-07-23023 July 1990 Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request L-90-271, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders1990-07-20020 July 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-335/90-09 & 50-389/90-09.Corrective Actions:Procedural Expectation Re Hanging & Removal of Deficiency Tags Will Be Reemphasized to Personnel Generating Work Orders ML17348A4141990-07-20020 July 1990 Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel ML17348A4191990-07-20020 July 1990 Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921 ML17348A4201990-07-20020 July 1990 Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr ML17223A8581990-07-19019 July 1990 Forwards Implementation Status of 10CFR50.62 Mod at Facility Re Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants ML17348A4171990-07-19019 July 1990 Forwards May 1990 Integrated Schedule Regulatory Rept for Plant ML17223A8491990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Transmitters Models 1153 Series B,1153 Series D & 1154 Mfg Prior to 890711 Supplied by Different Vendor ML17348A4121990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML17348A4251990-07-17017 July 1990 Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition ML17223A8521990-07-17017 July 1990 Forwards Addl Info Requested Re Generic Implications & Resolution of Control Element Assembly Failure at Plant.Encl Confirms Util Intent to Follow C-E Regulatory Response Group Action Program ML17348A4161990-07-16016 July 1990 Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units IR 05000250/19900131990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML17348A4151990-07-16016 July 1990 Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated ML20055G8641990-07-16016 July 1990 Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc ML17348A4041990-07-12012 July 1990 Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project ML17348A3921990-07-12012 July 1990 Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs ML17348A4321990-07-11011 July 1990 Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901 L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990 Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990 Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld ML17223A8421990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements IR 05000335/19900131990-07-0909 July 1990 Responds to Violations Noted in Insp Repts 50-335/90-13 & 50-389/90-13.Corrective Actions:Maint Personnel Counseled & Aware of Importance of Verifying Design Configuration Requirements ML17348A3941990-07-0909 July 1990 Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown ML17348A4311990-07-0505 July 1990 Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons ML17348A3881990-07-0505 July 1990 Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs ML17223A8391990-07-0303 July 1990 Forwards Results of Beach Survey Procedure & Reduction of Field Survey Data,Per Tech Spec 4.7.6.1.1.Unit 1 Updated Fsar,Section 2.4.2.2,concluded That Dune Condition Acceptable Per Tech Spec 5.1.3 1990-09-07
[Table view] |
Text
REGULATOR INFORMATION DISTRIBUTION STEM (R XDS>
ACCESS/QN NBR: 8606240371 DOC. DATE: 86/06/19 NOTARIZED: NO DOCKET 4:
FAC IL: 50-000 Genev ic Docket 05000000 50-250 Turkey Point Planti Unit 3i Flov ida Poroer and Ligh+ C 05000250 50-251 Turkey Point Plant. Unit 4i Florida Pa>ocr and Ligh+ C 05000251 50-335 St. Lucie Planti Unit li Flov ida Power Zc Light Co. 05000335 5O-389 St. Lucie Planti Unit 2i Flov ida Power 8c Light Co 05000389 AUTH. NAl'tE AUTHOR AFFXLIATI ON WOODY'. Q. Florida. Power ~c Light Co.
REC IP. NAME RECIPIENT AFFILIATION DENTQNi H. R. Office of Nuclear Reactov Regulation. Direc tov (post 851125
SUBJECT:
Requests pev mission to apply Code Case N-411 v e spectral damping values used in piping stress analysis instead of Section Ill> Div I> Table N-1230-1 values. Fee paid.
DISTRIBUTION CODE'001D COPXES RECEIVED: LTR i ENCL'IZE:
TITLE: QR Submittal: General Distribution NOTES:
RECXP IENT COPIES RECIPXENT COP IES ID CODE/NANE LTTR ENCL ID CODE/NANE LTTR ENCL pNR-A EB 1 1 PWR-B EB 1 PWR-A EICSB 2 2 PNR-B PEICSB 2 PNR-A FOB 1 1 PWR-B FOB PWR-A PD2 LA 1 0 PWR-B PD8 LA 0 PNR-A PD2 PD 01 5 5 PWR-B PD8 PD 01 5 5 licDONALD, D 1 TOURIGNY> E pNR-* PSB 1 PNR-B PEICSB PNR-A RSB 1 PNR-B RSB 1 INTERNAL: ADN/LFNB 1 0 ELD/HDSO 1 0 ELD/HDS2 1 0 N / HFT/TSCB 1 NRR/GRAS 0 REG FIL 04 1 RGN2 1 EXTERNAL: EGZcG BRUSQUE> S 1 1 LPDR 03 .2 2 NRC PDR 02 1 1 NSIC 05 1 1 TOTAL NUl']HER OF COPIES REQUIRED: LTTR 38 ENCL 32
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FLORIDA POWER & LIGHT COMPANY JQQ 1 9198B L-86-209 Mr. Harold R: Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Turkey Point Units 3 and 0 Docket Nos. 50-250 and 50-251 1
Re uest for ASME Code Case N-Oil "A royal Reference Documents:
- 1. NUREG-1061, Volume 2, "Report of the U. S. Nuclear Regulatory Commission Piping Review Committee, Evaluation of'Seismic Designs-A Review of Seismic Design. Requirements for Nuclear Power Piping."
- 2. L'etter from Thomas M. Novak (NRC) to D. W. Mazur (Washington Public Power Supply System), Docket No.50-060, WNP-I, "Approval of ASME Code Case N-Ol l."
In accordance with Article NCA-1100 of the ASME Section III Code, Florida Power R Light Company (FPL) requests Commission approval to apply Code Case N-Ol 1 as described below.
Code Case N-011 (copy attached) provides spectral damping values which may be used in lieu of Section III, Division I, Table N-1230-1 values. The original Section III values for spectral damping are identical to those considered acceptable to the Commission in Regulatory Guide 1.61. The N-Ol I damping values are endorsed by Reference I, which recommends that Regulatory Guide 1.61 be revised to incorporate the new criteria. FPL would utilize the new criteria on the St. Lucie and Turkey Point projects as follows:
- 1. Upon receipt of, Commission approval to utilize the subject Code Case, FPL would authorize the development of new response spectra curves which would reflect the application of the Pressure Vessel Research Committee (PVRC) criteria. Existing response spectra would be retained as Quality Assurance records however, since all existing piping 'stress analysis calculations of record make reference to them.
860$ 24037i g00250 PDR ADo PDR Ll:1 p /
PEOPLE ,.SERVING PEOPLE
I 8 ~
Mr. Harold R. Denton, Director L-86-249 Page two 2.'PL is presently engaged in a study to assess the cost feasibility of implementing a comprehensive support optimization (i.e., snubber reduction) program for the St. Lucie project. Should the study yield positive results regarding the cost effectiveness of such an undertaking, FPL may, at our option, utilize the PVRC damping values as the principal tool toward optimizing supports through reanalysis.
Depending on the outcome of the St. Lucie effort, a similar snubber reduction effort may be undertaken for Turkey Point Units 3 and 4.
- 3. Until support optimization efforts commence at any of the nuclear units, FPL may use the new PVRC damped response spectra on an interim basis to qualify anomalous piping conditions (such as may be discovered during inservice inspections) to avoid costly corrective actions such as physical modifications to piping or supports.
- 4. Code Case N-4I I may, at FPL's option, be applied to new systems analyzed by response spectrum methods. Code Case N-4I I may also be utilized to qualify proposed modifications to~existin systems.
Based on the use of Code Case N-4I I, all piping qualification analyses would continue to include, but not be limited to, verification that:
All affected piping supports are properly designed and capable of withstanding revised design loads.
Excessive pipe deflections are not introduced when supports are optimized (i.e., displacements would be checked to verify that proper clearances exist with respect to adjacent= structures, components and equipment). Pipe mounted equipment would also be checked to assure that the equipment could withstand the increased pipe motion.
r Postulated pipe break locations have been properly considered.
equipment nozzle loads are not adversely affected. 'ffected Each new analysis or reanalysis performed utilizing the PVRC damping values will include specific reference to Code Case N-4I I in the Quality Assurance Records associated with the calculation. For each anchor group (analysis package) where the code case is applied, the code case would be applied to the entire analysis (i.e., PVRC damping would not be mixed in a given analysis with Regulatory Guide l.6 I criteria).
Code Case N-4I I will be applied to systems analyzed by response spectrum methods, but not to those using time-history analysis methods.
MAS3/00 I /2
Mr. Harold R. Denton, Director L-86-249 Page three The mechanism for implementing the new criteria will be to document Commission approval to utilize Code Case N-4I I in a future amendment to the affected Final Safety Analysis Reports. Additionally, FPL would instruct its contractors performing piping stress analysis calculations to revise affected Quality Assurance Program procedures.
Please note that permission to utilize Code Case N-4I I damping values has already been granted to another nuclear project (see Reference 2). To support existing schedules for initiating support optimization efforts, FPL would appreciate receiving Commission approval to apply Code Case N-4I I criteria to St. Lucie Units I and 2 and Turkey Point Units 3 and 4 by August I5, l 986.
FPL Check No. I366 is attached in accordance with the fee schedule specified in IO CFR l70.2 I.
Very truly yours, C. O. Wood Group Vic resident Nuclear Energy COW/MAS/gp Attachments cc: Ashok C. Thadani, Director, PWR Project Directorate II8 Lester S. Rubenstein, Director, PWR Project Directorate II2 Dr. J. Nelson Grace, USNRC, Region II Harold F. Reis, Esquire, Newman & Holtzinger MAS3/00 I /3
CA5R N-411-1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: February 20, 1986 See Numerical Index for expfratfon and any reafffrmarfon darer.
Case N411-1 Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping Section I I I, Division 1 Inquiry: What alternatives to the damping values given in Section III, Division 1, Table N-1230-1 are acceptable for use in response spectra analysis of Class 1, 2, and 3 piping?
3 Reply: It is the opinion of the Committee that for as I I
Section III, Division 1, Class 1, 2, and 3 construction, C 2 I the damping value for response spectra analysis of piping CL E I shown in Fig. 1 may be used as an alternative to those O I
I given in Table N-1230.1. 1 I
The damping value in Fig. 1 is applicable to both I I
Operating Basis Earthquakes and Safe Shutdown Earth-0 quakes a'nd is independent of pipe diameter. 0 10 20 33 The damping value in Fig. 1 is also applicable to other Frequency, Hz response spectra-type dynamic loads for which the response spectra is generated after being filtered through the building structure. FIG. 1 DAMPING VALUES FOR RESPONSE Damping values to be used with spectra with responses .SPECTRA ANALYSIS OF PIPING above 33 Hs shall be evaluated and designated by the designer.
This Case number shall be shown in the documenta.
tion for this analysis and on the Code Data Report.
817 SUPP. 13- NC