|
|
(3 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 05/23/1990 | | | issue date = 05/23/1990 |
| | title = Application for Amend to License DPR-18,revising Tech Spec Pages 4.2-2 & 4.2-4 Re Inservice Insp & Basis Section Concerning Steam Generator Tube & Sleeve Repair Criteria | | | title = Application for Amend to License DPR-18,revising Tech Spec Pages 4.2-2 & 4.2-4 Re Inservice Insp & Basis Section Concerning Steam Generator Tube & Sleeve Repair Criteria |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = JOHNSON A R | | | addressee name = Johnson A |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000244 | | | docket = 05000244 |
Line 14: |
Line 14: |
| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 4 | | | page count = 4 |
| | | project = |
| | | stage = Request |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:A,CCELERATED DIUTIONDEMONSTPA.TION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9005310499 DOC.DATE: | | {{#Wiki_filter:A,CCELERATED DI UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 90/05/23NOTARIZED: | | ACCESSION NBR:9005310499 DOC.DATE: 90/05/23 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp. |
| NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R |
| Rochester Gas6ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | |
| ProjectDirectorate I-3DOCKET05000244R
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendtoLicenseDPR-18,revising TechSpecPage4.2-4.DISTRIBUTION CODE:A054DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | Application for amend to License DPR-18,revising Tech Spec I Page 4.2-4. |
| SteamGenerator SleevingReviewforPWR'sNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | DISTRIBUTION CODE: A054D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: OR Submittal: Steam Generator Sleeving Review for PWR's S |
| IDS05000244/RECIPIENT IDCODE/NAME PDl-3LAJOHNSON,A INTERNAL:
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 |
| AEODNRR/DOEA/OGCB11 NRR/PMAS/ILRB12 OC/LMFILEEXTERNAL'PDR NSICCOPIESLTTRENCL101111101010111111RECIPIENT IDCODE/NAME PD1-3PDNRR/DET/ECMB 9HNRR/DST/SPLB 8DNUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB NRCPDRCOPIESLTTRENCL33101011111111DDDNOTETOALL"RIDS"RECIPIENTS:
| | / |
| PLEASEHELPUSTOREDUCEWASTE!CONTACI'HE DOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 0 PD1-3 PD 3 3 D JOHNSON,A 1 1 D |
| LTTR18ENCL12/0D NEwAaaKAwfuYORK';5YAYE///!////////I g!///I/////I
| | INTERNAL: AEOD 1 1 NRR/DET/ECMB 9H 1 0 NRR/DOEA/OGCB11 1 0 NRR/DST/SPLB 8D 1 0 NRR/PMAS/ILRB12 1 0 NUDOCS-ABSTRACT 1 1 OC/L M 1 0 OGC/HDS2 1 1 FILE 1 1 RES/DSIR/EIB 1 1 EXTERNAL'PDR 1 1 NRC PDR 1 1 NSIC 1 1 D |
| /I///////'//////////// | | / |
| //////Z////I//////I ZZROCHESTER GASANDELECTRICCORPORATION oegEASTAVENUE,ROCHESTER, NY.1464g0001May23,1990TELEPHONE AREACOOKYIO546.2700U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-3Washington, D.C.20555 | | 0 D |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 12 |
| | |
| | NEw |
| | ///!////////I !///I/////I AaaK Awfu g |
| | /I/// ////'//////////// |
| | //////Z ////I//////I ROCHESTER GAS AND ELECTRIC CORPORATION o eg EAST AVENUE, ROCHESTER, N Y. 1464g 0001 ZZ YORK '; |
| | 5YAYE May 23, 1990 TELEPHONE AREA COOK YIO 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Technical Specification Paragraphs 4.2.1.4.a, 4.2.1.4.b andBasisR.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Technical Specification Paragraphs 4.2.1.4.a, 4.2.1.4.b and Basis R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Johnson:== |
| | |
| | License Amendment No. 35 (issued April 24, 1989) added paragraphs 4.2.1.4.a, 4.2.1.4.b and a second paragraph in the Basis section regarding steam generator tube and sleeve repair criteria. |
| | License Amendment No. 37 (issued May 30, 1989) regarding the Inservice Inspection Program for snubbers, also made changes to Section 4.2 of the Technical Specifications. |
| | The request for License Amendment for the snubber ISI Program was submitted prior to the request for steam generator tube and sleeve repair criteria. That License Amendment application consequently did not include paragraphs 4.2.1.4.a and 4.2.1.4.b or paragraph 2 of the Basis. When Amendment No. 37 was approved, page 4.2-2 was approved without paragraphs 4.2.1.4.a and 4.2.1.4.b and page 4.2-3 was approved without the complete Basis section. |
| | RGGE requests that Technical Specification page 4.2-2 and new page 4.2-4, containing the remainder of the Basis, be issued reinstating these three approved paragraphs (page 4.2-3 remains the same). |
| | In the meantime, RGGE has been, and will continue to, abide by the provisions of approved License Amendment No. 35 paragraphs 4.2.1.4.a and 4.2.1.4.b. |
| | Very truly yours, Robert C. Me redy Division Manager Nuclear Production GJWN105 o~4 9005320499 900523 nOOCK 05000Z44 P PDC |
| | |
| | ~c 1 |
| | E I |
|
| |
|
| ==DearMr.Johnson:==
| | xc: Mr. Allen R. Johnson (Mail Stop 14Dl) |
| LicenseAmendment No.35(issuedApril24,1989)addedparagraphs 4.2.1.4.a, 4.2.1.4.b andasecondparagraph intheBasissectionregarding steamgenerator tubeandsleeverepaircriteria.
| | Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}} |
| LicenseAmendment No.37(issuedMay30,1989)regarding theInservice Inspection Programforsnubbers, alsomadechangestoSection4.2oftheTechnical Specifications.
| |
| TherequestforLicenseAmendment forthesnubberISIProgramwassubmitted priortotherequestforsteamgenerator tubeandsleeverepaircriteria.
| |
| ThatLicenseAmendment application consequently didnotincludeparagraphs 4.2.1.4.a and4.2.1.4.b orparagraph 2oftheBasis.WhenAmendment No.37wasapproved, page4.2-2wasapprovedwithoutparagraphs 4.2.1.4.a and4.2.1.4.b andpage4.2-3wasapprovedwithoutthecompleteBasissection.RGGErequeststhatTechnical Specification page4.2-2andnewpage4.2-4,containing theremainder oftheBasis,beissuedreinstating thesethreeapprovedparagraphs (page4.2-3remainsthesame).Inthemeantime, RGGEhasbeen,andwillcontinueto,abidebytheprovisions ofapprovedLicenseAmendment No.35paragraphs 4.2.1.4.a and4.2.1.4.b.
| |
| Verytrulyyours,RobertC.MeredyDivisionManagerNuclearProduction GJWN1059005320499 900523nOOCK05000Z44PPDCo~4
| |
| ~c1EI xc:Mr.AllenR.Johnson(MailStop14Dl)ProjectDirectorate I-3Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector}}
| |
Similar Documents at Ginna |
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
A,CCELERATED DI UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9005310499 DOC.DATE: 90/05/23 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R
SUBJECT:
Application for amend to License DPR-18,revising Tech Spec I Page 4.2-4.
DISTRIBUTION CODE: A054D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: OR Submittal: Steam Generator Sleeving Review for PWR's S
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244
/
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 0 PD1-3 PD 3 3 D JOHNSON,A 1 1 D
INTERNAL: AEOD 1 1 NRR/DET/ECMB 9H 1 0 NRR/DOEA/OGCB11 1 0 NRR/DST/SPLB 8D 1 0 NRR/PMAS/ILRB12 1 0 NUDOCS-ABSTRACT 1 1 OC/L M 1 0 OGC/HDS2 1 1 FILE 1 1 RES/DSIR/EIB 1 1 EXTERNAL'PDR 1 1 NRC PDR 1 1 NSIC 1 1 D
/
0 D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 12
NEw
///!////////I !///I/////I AaaK Awfu g
/I/// ////'////////////
//////Z ////I//////I ROCHESTER GAS AND ELECTRIC CORPORATION o eg EAST AVENUE, ROCHESTER, N Y. 1464g 0001 ZZ YORK ';
5YAYE May 23, 1990 TELEPHONE AREA COOK YIO 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Technical Specification Paragraphs 4.2.1.4.a, 4.2.1.4.b and Basis R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
License Amendment No. 35 (issued April 24, 1989) added paragraphs 4.2.1.4.a, 4.2.1.4.b and a second paragraph in the Basis section regarding steam generator tube and sleeve repair criteria.
License Amendment No. 37 (issued May 30, 1989) regarding the Inservice Inspection Program for snubbers, also made changes to Section 4.2 of the Technical Specifications.
The request for License Amendment for the snubber ISI Program was submitted prior to the request for steam generator tube and sleeve repair criteria. That License Amendment application consequently did not include paragraphs 4.2.1.4.a and 4.2.1.4.b or paragraph 2 of the Basis. When Amendment No. 37 was approved, page 4.2-2 was approved without paragraphs 4.2.1.4.a and 4.2.1.4.b and page 4.2-3 was approved without the complete Basis section.
RGGE requests that Technical Specification page 4.2-2 and new page 4.2-4, containing the remainder of the Basis, be issued reinstating these three approved paragraphs (page 4.2-3 remains the same).
In the meantime, RGGE has been, and will continue to, abide by the provisions of approved License Amendment No. 35 paragraphs 4.2.1.4.a and 4.2.1.4.b.
Very truly yours, Robert C. Me redy Division Manager Nuclear Production GJWN105 o~4 9005320499 900523 nOOCK 05000Z44 P PDC
~c 1
E I
xc: Mr. Allen R. Johnson (Mail Stop 14Dl)
Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector