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| {{#Wiki_filter:&Wu.W A.." SA..o,.ov H. a Elc* 0"W- -&*WUMAE 3881 V"WErnWVO RoadHff" SC 20WOa: 843W ? 14F: 843 857 1319Serial: RNP.W113.0089 10 CFR 50.90AUG 2 2 2013ATTN: Document CWrol DeskU.S. Regulaory Commission wasimngton, DC 2058-0001 H. B. RO8INSON STEAM ELECTRIC PLANT, UNIT NO. 2DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23SUPPLEMENTAL SUBMITTAL TO CORRECT TS PAGES REGARDING REQUEST FORREVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBESAPE LECION AM. 6PP!AIQN QpE MMAWN ALTERNATE REPARN RTEIByl,*t daled 29,2012, (Pgncyw* | | {{#Wiki_filter:&Wu.W A.." SA..o,.ov H. a Elc* 0"W- -&*WUMA E 3881 V"WErnWVO Road Hff" SC 20WO a: 843W ? 14 F: 843 857 1319 Serial: RNP.W113.0089 10 CFR 50.90 AUG 2 2 2013 ATTN: Document CWrol Desk U.S. Regulaory Commission wasimngton, DC 2058-0001 H. B. RO8INSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 SUPPLEMENTAL SUBMITTAL TO CORRECT TS PAGES REGARDING REQUEST FOR REVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBE SAPE LECION AM. 6PP!AIQN QpE MMAWN ALTERNATE REPARN RTEI Byl,*t daled 29,2012, (Pgncyw* Docmens Access and Management Sytem (AAMS) M u No. WLI2S );d wtAo 10 CFRW5.90, Carolina Power and Light Cormpn requested an amendmetqto he ifB. Rb: no Steami6 6" c" ~stU NO.rewwedfaclly opsrutln Ucane bPft-23.lAppendlx A, T~chhkcI Spcfctot(TSY SOctlo 5.5.9, Steamn Generator (5(3) Program.By leter dated February 4,2013, (ADAMS Accession No. ML13017A288) the NRC stff reqwiesed oddltjonl Informatli (RAJ) needed to continue its review of the proposed liceme By etter I d Apt", 2013 (ADAMAoessa'aon No. MbLt&123Ai221) |
| Docmens Access and Management Sytem(AAMS) M u No. WLI2S );d wtAo 10 CFRW5.90, Carolina Power and LightCormpn requested an amendmetqto he ifB. Rb: no Steami6 6" c" ~stU NO.rewwedfaclly opsrutln Ucane bPft-23.lAppendlx A, T~chhkcI Spcfctot(TSY SOctlo5.5.9, Steamn Generator (5(3) Program.By leter dated February 4,2013, (ADAMS Accession No. ML13017A288) the NRC stffreqwiesed oddltjonl Informatli (RAJ) needed to continue its review of the proposed licemeBy etter I d Apt", 2013 (ADAMAoessa'aon No. MbLt&123Ai221) | | Duke Energy Progress, Inc. formerly known as CaroWnaPowwnd Light Company provided It response to the NRCs request for additional information. |
| Duke Energy Progress, Inc. formerly known as CaroWnaPowwnd Light Company provided It response to the NRCsrequest for additional information. | | Atteched please find reilacment TS pages (pages 5.0-13 and 5.0-28)for the co n d TS pages in A#ment 2 to the 9,2013 letter. The eplaemen of these page does not affect the concusions of elther* 10-CFR 50.92 No $ Oa Hazards Consderation imaem"InaIo ortlhe Envirompiotol~ |
| Atteched please find reilacment TS pages (pages 5.0-13 and 5.0-28)for the co n d TSpages in A#ment 2 to the 9,2013 letter. The eplaemen of these page does notaffect the concusions of elther* 10-CFR 50.92 No $ Oa Hazards Consderation imaem"InaIo ortlhe Envirompiotol~ | | Cakk ofmncnluided VAIft u losur to. the April9;W2013 submittal leter. There awe no other changes or addition to the Abd emrs to April 9, 2013 lettW:r h presesn the proposed TS page markups, toe retyped TS pages, and mark.ed up TS Buse pag (for Wnform on oty This documnent conlltains no new Regulatory Commitmenft. |
| Cakk ofmncnluided VAIft u losur to. the April9;W2013 submittal leter. There awe no other changes or addition to the Abd emrs to April 9, 2013lettW:r h presesn the proposed TS page markups, toe retyped TS pages, and mark.ed upTS Buse pag (for Wnform on otyThis documnent conlltains no new Regulatory Commitmenft. | | In accordance w*th10 COR 50i1(ti) aop ofl thsaplcain sbe poiddthstsib SaeOf South Carolina. |
| In accordance w*th10 COR 50i1(ti) aop ofl thsaplcain sbe poiddthstsib SaeOfSouth Carolina. | | f you' haew an tiiosredI p uir~lt, please contact Mr. Richad Iiil$we~ upryso -ces g/ tryPr~rs~ |
| f you' haew an tiiosredI p uir~lt, please contact Mr. RichadIiil$we~ | | t~438-9i29 H11" United StlMt Nuclear Regulatory Commi*Aon Sewd: FRNP.x13-0069 Poew 2 of 2 1 declae under penalty of pe"ur tha fth foregong ts Mme a" correct. Executed On:______sin-eel, Sharon WheI!)Pavytou**-WK _ Suipport services -Nuclear SWP/$c |
| upryso -ces g/ tryPr~rs~ | |
| t~438-9i29 H11" United StlMt Nuclear Regulatory Commi*Aon Sewd: FRNP.x13-0069 Poew 2 of 21 declae under penalty of pe"ur tha fth foregong ts Mme a" correct. | |
| Executed On:______ | |
| sin-eel,Sharon WheI!)Pavytou**
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| -WK _ Suipport services | |
| -NuclearSWP/$c | |
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| Rp"lacemen Pages for TS Page 5.0-13 anid 5.0-28 of Afttachment 2 of RNP-RAil 3-0030.cc:M.- Af,. E. Jenkins. | | Rp"lacemen Pages for TS Page 5.0-13 anid 5.0-28 of Afttachment 2 of RNP-RAil 3-0030.cc:M.- Af,. E. Jenkins. MangrW nfecftiou an Radioactiv Wast Mangeen Section (SC)Mr V. M. McCrea, NRC Regom If Mr. S. P. ungm, NRC Prje Manaer, NRR NRC Resident Inspecto. |
| MangrW nfecftiou an Radioactiv Wast Mangeen Section (SC)Mr V. M. McCrea, NRC Regom IfMr. S. P. ungm, NRC Prje Manaer, NRR NRCResident Inspecto. | | HORSEP Mr. A. Wln, Attorney General (SC) |
| HORSEPMr. A. Wln, Attorney General (SC)
| | Unftd $Wms Nodge Regpdioy Comm*Ww Attschmnt bo Ser: RNP4WAI3-OOS 3 PsgW, xincudnt Vcoverpeg* |
| Unftd $Wms Nodge Regpdioy Comm*WwAttschmnt bo Ser: RNP4WAI3-OOS 3 PsgW, xincudnt Vcoverpeg* | | ATTACHMENT ftpkmvnwi Pap* for TS Paoes &.0. 13 anW 5.0-28 of Attachment 2 of RNP-RAI3-0030 Programs and Manuals 5.5 5.5 PBoWns and MA ... ..5.5.9 amDO1SO Mal EfggNM (continued) |
| ATTACHMENT ftpkmvnwi Pap* for TS Paoes &.0. 13 anW 5.0-28of Attachment 2 of RNP-RAI3-0030 Programs and Manuals5.55.5 PBoWns and MA ... ..5.5.9 amDO1SO Mal EfggNM(continued) | | C. Provision for SG tube pluggin criteia. Tubes found by Inservice inspection to contain flaws with a depth equal to or exceeding the following criterta sal be plugged: 47% of the nominal tube wall thickness If the next inspection inlerval of that tube Is< 12 month and a 2% reduction In the plugging criteria for each 12 month period until the next inspection of the I tube.The following anler tube plugging criteria shall be applied as an alternative to the precd citeria: Tube with -h edloed flaws located greater than 18.11 inches below the top of the tubhe do not require plugging. |
| C. Provision for SG tube pluggin criteia. | | Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 18.11 inches below the top of the tubeshest shall be plugged upon daetctio.d. fPvso for S itube inspections. |
| Tubes found by Inservice inspection to contain flaws with a depth equal to or exceeding the following criterta sal be plugged: | | Periodic SG ue inspections Shall be perfore. The number and portions of the Iubes Inspected and methods of inspection shall be performed wth the objectve of detecting flaws of any type (e.g., volumetric flaws, axial and ia cracks) that may be eiset awon the length of the tube, from the ftu 4*ubhtW weld at the tube Inlet to the tube4otubesheet weld at the tube outlet and that may satisfy the applicable tube plugg criteria. |
| 47% of the nominal tube wall thickness If the nextinspection inlerval of that tube Is< 12 month and a 2% reduction In theplugging criteria for each 12 month period until the next inspection of the Itube.The following anler tube plugging criteria shall be applied as analternative to the precd citeria:Tube with -h edloed flaws located greater than 18.11 inches belowthe top of the tubhe do not require plugging. | | The tub4otubesheht wekl is not part of the tube. In addition to fmeen the requirements of d.1, d.2, and d.3 below, the Inspection scope, inspection methods, and Inspection Intervals shal be such as to ensure that SQ tube integrity Is maintained until the neod SO Inspection. |
| Tubes with service-induced flaws located in the portion of the tube from the top of thetubesheet to 18.11 inches below the top of the tubeshest shall be pluggedupon daetctio. | | A degradation aseasment shall be performed to dOemine the type and location of flews to which the tubes may be susceptible ard, based on this assessment, to determine which inspection methods need to be employed and at what locations. |
| : d. fPvso for S itube inspections.
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| Periodic SG ue inspections Shall beperfore. | |
| The number and portions of the Iubes Inspected and methodsof inspection shall be performed wth the objectve of detecting flaws of anytype (e.g., volumetric flaws, axial and ia cracks) that may beeiset awon the length of the tube, from the ftu 4*ubhtW weld at thetube Inlet to the tube4otubesheet weld at the tube outlet and that maysatisfy the applicable tube plugg criteria. | |
| The tub4otubesheht wekl isnot part of the tube. In addition to fmeen the requirements of d.1, d.2, andd.3 below, the Inspection scope, inspection | |
| : methods, and Inspection Intervals shal be such as to ensure that SQ tube integrity Is maintained until the neod SO Inspection.
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| A degradation aseasment shall be performed to dOemine the type and location of flews to which the tubes may besusceptible ard, based on this assessment, to determine which inspection methods need to be employed and at what locations. | |
| : 1. Inspect 100% of the tubes in each SG during the firstefueling outage following SG Installation. | | : 1. Inspect 100% of the tubes in each SG during the firstefueling outage following SG Installation. |
| : 2. After toe first refueling outage following SG installation, inspect eachSO at West every 48 effecti full power monft or at least everyother refueling outae (Whichever results In more *equentinspections). | | : 2. After toe first refueling outage following SG installation, inspect each SO at West every 48 effecti full power monft or at least every other refueling outae (Whichever results In more *equent inspections). |
| In additin, the minimum number of tubes inspected ateach scheduled Inspection shall be te number of tubes in at SOsdvided by the number of SG inspection ouages sheduled in eachInspecion period as defined In a, b, and c below. If a degradation aseesIete indicates the potential for a type of degradation to occurat a location not previous Inspected with a technique capable ofdetecting Othi type of degradation at Othi location and that may satisfyrvNO AMA I5Ao.HOMP5.0-13Aftvwxftnent No. | | In additin, the minimum number of tubes inspected at each scheduled Inspection shall be te number of tubes in at SOs dvided by the number of SG inspection ouages sheduled in each Inspecion period as defined In a, b, and c below. If a degradation aseesIete indicates the potential for a type of degradation to occur at a location not previous Inspected with a technique capable of detecting Othi type of degradation at Othi location and that may satisfy rvNO AMA I 5Ao.HOMP 5.0-13 Aftvwxftnent No. |
| Reportng Requirements 5.65.6 Rbork Rakaum-nta (cotnud5.8.7 Tendon IvMO M FfRema, Notification of a pending sample tendon test, along with detailedacceptice | | Reportng Requirements 5.6 5.6 Rbork Rakaum-nta (cotnud 5.8.7 Tendon IvMO M FfRem a, Notification of a pending sample tendon test, along with detailed acceptice criteria, shae be submted to the NRC at last two month prior to the actual test b. A report containing the sample tendon test eveaation shall be submitted to the NRC within six monft of condkci te test 5.8.8 StM eE nom TUS .mscionM A report shall be suWbmitd within 180 days after the initial entry into MODE 4 followin completion of an Inspection performed in accordance with the Specification 5.5.9, Stam Generator (SO) Program. The report shell incluie: a. The scope of inspectons performed on each $0.b. Degradation mehnssfound. |
| : criteria, shae be submted to the NRC at last two monthprior to the actual testb. A report containing the sample tendon test eveaation shall besubmitted to the NRC within six monft of condkci te test5.8.8 StM eE nom TUS .mscionMA report shall be suWbmitd within 180 days after the initial entry into MODE 4followin completion of an Inspection performed in accordance with theSpecification 5.5.9, Stam Generator (SO) Program.
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| The report shell incluie:a. The scope of inspectons performed on each $0.b. Degradation mehnssfound. | |
| : c. 1u em tchniques utilized for each degradation mechanism. | | : c. 1u em tchniques utilized for each degradation mechanism. |
| : d. Location, orientation (If linewa), | | : d. Location, orientation (If linewa), and measured sizes (If available) of service Induced indications. |
| and measured sizes (If available) ofservice Induced indications. | | : e. Number of tube plugged during the Inspection outage for each degadation mechanism. |
| : e. Number of tube plugged during the Inspection outage for eachdegadation mechanism. | | : f. The number vnd percentage of tubes plugged to date, and the effctive pluggng percentaep In each steam geerwator. |
| : f. The number vnd percentage of tubes plugged to date, and the effctivepluggng percentaep In each steam geerwator. | | : g. The results of condition monitoring, inclufd Ot results of tube pulls an isu test.h. The primary to econdry leakage rate observd In each SG (If It is not practical to th leakage to an niiulu SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG)during the cycle preceting the Inspection that Is the subject of the repor.I. The aluMl accident induced leakage rate from the portion of the tubes below 18.1 Inchxem fom the top of the tubesheet for the most limiting accident in the most lmiting SG. In addition, If the calculated accident induced lakap rate from the most imitng ascldent is les than 1.87 times the maximum operational primary to secondary lakag rate. the report should describe how it was determined, and H SE Unit No. 2 5.0-28 Amerximent No.}} |
| : g. The results of condition monitoring, inclufd Ot results of tube pulls anisu test.h. The primary to econdry leakage rate observd In each SG (If It is notpractical to th leakage to an niiulu SG, the entire primary tosecondary leakage should be conservatively assumed to be from one SG)during the cycle preceting the Inspection that Is the subject of the repor.I. The aluMl accident induced leakage rate from the portion of the tubesbelow 18.1 Inchxem fom the top of the tubesheet for the most limitingaccident in the most lmiting SG. In addition, If the calculated accidentinduced lakap rate from the most imitng ascldent is les than 1.87times the maximum operational primary to secondary lakag rate. thereport should describe how it was determined, andH SE Unit No. 25.0-28Amerximent No.}} | |
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Category:Letter
MONTHYEARIR 05000261/20244012024-09-11011 September 2024 Security Baseline Inspection Report 05000261/2024401 ML24242A2612024-08-29029 August 2024 Operator Licensing Examination Approval 05000261/2024301 IR 05000261/20240052024-08-22022 August 2024 Updated Inspection Plan for H.B. Robinson Steam Electric Plant - Report 05000261/2024005 ML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area IR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230062024-02-28028 February 2024 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 - Report 05000261-2023006 IR 05000261/20243012024-02-0606 February 2024 – Notification of Licensed Operator Initial Examination 05000261/2024301 ML24033A0592024-02-0202 February 2024 Response to Request for Additional Information License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology IR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 2024-09-11
[Table view] Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 32019-07-16016 July 2019 Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3 ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. ML15222B1752015-09-0808 September 2015 Issuance of Amendment to Modify Technical Specification 3.8.1, Diesel Generator Testing Requirements RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. RNP-RA/15-0026, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-04-0101 April 2015 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication RNP-RA/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation2014-02-10010 February 2014 License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation ML13198A3672013-08-29029 August 2013 Issuance of an Amendment to Revise the Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) RNP-RA/13-0089, Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria2013-08-22022 August 2013 Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria RNP-RA/13-0002, License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements2013-06-0707 June 2013 License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*)2012-08-29029 August 2012 License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) ML11342A1652011-12-29029 December 2011 Issuance of an Amendment on Technical Specifications Related to Use of Areva'S M5 Advanced Alloy in Fuel Cladding and Fuel Assembly Components RNP-RA/10-0096, Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel2010-10-20020 October 2010 Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel ML1008303302010-03-25025 March 2010 Issuance of Amendment Regarding Technical Specifications Changes Related to the Chemical and Volume Control System RNP-RA/10-0024, Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS)2010-03-22022 March 2010 Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS) RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation ML0936312122009-12-16016 December 2009 Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/09-0024, Transmittal of Technical Specifications Bases Revisions2009-04-16016 April 2009 Transmittal of Technical Specifications Bases Revisions ML0813403232008-07-23023 July 2008 Issuance of Amendment Regarding the Incorporation of Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-448, Revision 3, Control Room Habitability. ML0815402792008-06-19019 June 2008 Tech Spec Pages for Amendment 218 Regarding Administrative Changes to the Operating License and Technical Specifications ML0803300542008-01-29029 January 2008 Tech Spec Pages for Amendment 217 to Make a One-time Change to Technical Specification (TS) 3.1.7 Rod Position Indication. ML0726102012007-09-19019 September 2007 Technical Specification, Correction to Technical Specification Page Issued with Amendment No. 215 Issued on June 15, 2007 ML0725706282007-09-18018 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 216 Issued on July 16, 2007 RNP-RA/07-0095, Correction to Technical Specifications Page in Amendment 2162007-09-12012 September 2007 Correction to Technical Specifications Page in Amendment 216 ML0720102362007-07-16016 July 2007 Tech Spec Pages for Amendment 216 to Adopt Technical Specifications Task Force (TSTF) Standard TS Change Traveler, TSTF-447, Using the Consolidated Line Item Improvement Process ML0717202542007-06-15015 June 2007 Technical Specifications Changes Related to Containment Peak Pressure ML0709900232007-04-0404 April 2007 Technical Specifications, Changes Surveillance Requirement (SR) 3.5.2.6 RNP-RA/07-0032, Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-22022 March 2007 Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria RNP-RA/07-0023, Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-13013 March 2007 Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria ML0628404592006-10-0404 October 2006 Tech Spec Pages for Amendment 208 Regarding Emergency Diesel Generator or Automatic Trips Bypass TS 3.8.1 ML0627100222006-09-22022 September 2006 Technical Specification Amendment No. 210 - H.B. Robinson, Unit 2 - Issuance of Amendment and Partial Denial Reactor Protection System and Engineered Safety Feature Actuation System Instrumentation Tables ML0627005192006-09-20020 September 2006 Technical Specifications, Amendment, Methodology for Large Break Loss-of-Coolant Accident RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure2006-07-17017 July 2006 Request for Technical Specifications, Change Related to Containment Peak Pressure ML0621900412006-07-11011 July 2006 Technical Specifications, Alternate Source Term for the loss-of-coolant RNP-RA/06-0046, Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System2006-06-0101 June 2006 Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-05-30030 May 2006 Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0610805222006-04-11011 April 2006 H. B. Robinson, Unit 2 - Request for Technical Specification Change to Core Operating Limits Report References RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.2006-03-31031 March 2006 ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis. ML0524205242005-08-25025 August 2005 Tech Spec Pages for Amendment 206 DC Sources - Operation and Shutdown RNP-RA/05-0062, Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating2005-07-13013 July 2005 Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating 2023-08-29
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&Wu.W A.." SA..o,.ov H. a Elc* 0"W- -&*WUMA E 3881 V"WErnWVO Road Hff" SC 20WO a: 843W ? 14 F: 843 857 1319 Serial: RNP.W113.0089 10 CFR 50.90 AUG 2 2 2013 ATTN: Document CWrol Desk U.S. Regulaory Commission wasimngton, DC 2058-0001 H. B. RO8INSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 SUPPLEMENTAL SUBMITTAL TO CORRECT TS PAGES REGARDING REQUEST FOR REVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBE SAPE LECION AM. 6PP!AIQN QpE MMAWN ALTERNATE REPARN RTEI Byl,*t daled 29,2012, (Pgncyw* Docmens Access and Management Sytem (AAMS) M u No. WLI2S );d wtAo 10 CFRW5.90, Carolina Power and Light Cormpn requested an amendmetqto he ifB. Rb: no Steami6 6" c" ~stU NO.rewwedfaclly opsrutln Ucane bPft-23.lAppendlx A, T~chhkcI Spcfctot(TSY SOctlo 5.5.9, Steamn Generator (5(3) Program.By leter dated February 4,2013, (ADAMS Accession No. ML13017A288) the NRC stff reqwiesed oddltjonl Informatli (RAJ) needed to continue its review of the proposed liceme By etter I d Apt", 2013 (ADAMAoessa'aon No. MbLt&123Ai221)
Duke Energy Progress, Inc. formerly known as CaroWnaPowwnd Light Company provided It response to the NRCs request for additional information.
Atteched please find reilacment TS pages (pages 5.0-13 and 5.0-28)for the co n d TS pages in A#ment 2 to the 9,2013 letter. The eplaemen of these page does not affect the concusions of elther* 10-CFR 50.92 No $ Oa Hazards Consderation imaem"InaIo ortlhe Envirompiotol~
Cakk ofmncnluided VAIft u losur to. the April9;W2013 submittal leter. There awe no other changes or addition to the Abd emrs to April 9, 2013 lettW:r h presesn the proposed TS page markups, toe retyped TS pages, and mark.ed up TS Buse pag (for Wnform on oty This documnent conlltains no new Regulatory Commitmenft.
In accordance w*th10 COR 50i1(ti) aop ofl thsaplcain sbe poiddthstsib SaeOf South Carolina.
f you' haew an tiiosredI p uir~lt, please contact Mr. Richad Iiil$we~ upryso -ces g/ tryPr~rs~
t~438-9i29 H11" United StlMt Nuclear Regulatory Commi*Aon Sewd: FRNP.x13-0069 Poew 2 of 2 1 declae under penalty of pe"ur tha fth foregong ts Mme a" correct. Executed On:______sin-eel, Sharon WheI!)Pavytou**-WK _ Suipport services -Nuclear SWP/$c
Attachment:
Rp"lacemen Pages for TS Page 5.0-13 anid 5.0-28 of Afttachment 2 of RNP-RAil 3-0030.cc:M.- Af,. E. Jenkins. MangrW nfecftiou an Radioactiv Wast Mangeen Section (SC)Mr V. M. McCrea, NRC Regom If Mr. S. P. ungm, NRC Prje Manaer, NRR NRC Resident Inspecto.
HORSEP Mr. A. Wln, Attorney General (SC)
Unftd $Wms Nodge Regpdioy Comm*Ww Attschmnt bo Ser: RNP4WAI3-OOS 3 PsgW, xincudnt Vcoverpeg*
ATTACHMENT ftpkmvnwi Pap* for TS Paoes &.0. 13 anW 5.0-28 of Attachment 2 of RNP-RAI3-0030 Programs and Manuals 5.5 5.5 PBoWns and MA ... ..5.5.9 amDO1SO Mal EfggNM (continued)
C. Provision for SG tube pluggin criteia. Tubes found by Inservice inspection to contain flaws with a depth equal to or exceeding the following criterta sal be plugged: 47% of the nominal tube wall thickness If the next inspection inlerval of that tube Is< 12 month and a 2% reduction In the plugging criteria for each 12 month period until the next inspection of the I tube.The following anler tube plugging criteria shall be applied as an alternative to the precd citeria: Tube with -h edloed flaws located greater than 18.11 inches below the top of the tubhe do not require plugging.
Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 18.11 inches below the top of the tubeshest shall be plugged upon daetctio.d. fPvso for S itube inspections.
Periodic SG ue inspections Shall be perfore. The number and portions of the Iubes Inspected and methods of inspection shall be performed wth the objectve of detecting flaws of any type (e.g., volumetric flaws, axial and ia cracks) that may be eiset awon the length of the tube, from the ftu 4*ubhtW weld at the tube Inlet to the tube4otubesheet weld at the tube outlet and that may satisfy the applicable tube plugg criteria.
The tub4otubesheht wekl is not part of the tube. In addition to fmeen the requirements of d.1, d.2, and d.3 below, the Inspection scope, inspection methods, and Inspection Intervals shal be such as to ensure that SQ tube integrity Is maintained until the neod SO Inspection.
A degradation aseasment shall be performed to dOemine the type and location of flews to which the tubes may be susceptible ard, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 1. Inspect 100% of the tubes in each SG during the firstefueling outage following SG Installation.
- 2. After toe first refueling outage following SG installation, inspect each SO at West every 48 effecti full power monft or at least every other refueling outae (Whichever results In more *equent inspections).
In additin, the minimum number of tubes inspected at each scheduled Inspection shall be te number of tubes in at SOs dvided by the number of SG inspection ouages sheduled in each Inspecion period as defined In a, b, and c below. If a degradation aseesIete indicates the potential for a type of degradation to occur at a location not previous Inspected with a technique capable of detecting Othi type of degradation at Othi location and that may satisfy rvNO AMA I 5Ao.HOMP 5.0-13 Aftvwxftnent No.
Reportng Requirements 5.6 5.6 Rbork Rakaum-nta (cotnud 5.8.7 Tendon IvMO M FfRem a, Notification of a pending sample tendon test, along with detailed acceptice criteria, shae be submted to the NRC at last two month prior to the actual test b. A report containing the sample tendon test eveaation shall be submitted to the NRC within six monft of condkci te test 5.8.8 StM eE nom TUS .mscionM A report shall be suWbmitd within 180 days after the initial entry into MODE 4 followin completion of an Inspection performed in accordance with the Specification 5.5.9, Stam Generator (SO) Program. The report shell incluie: a. The scope of inspectons performed on each $0.b. Degradation mehnssfound.
- c. 1u em tchniques utilized for each degradation mechanism.
- d. Location, orientation (If linewa), and measured sizes (If available) of service Induced indications.
- e. Number of tube plugged during the Inspection outage for each degadation mechanism.
- f. The number vnd percentage of tubes plugged to date, and the effctive pluggng percentaep In each steam geerwator.
- g. The results of condition monitoring, inclufd Ot results of tube pulls an isu test.h. The primary to econdry leakage rate observd In each SG (If It is not practical to th leakage to an niiulu SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG)during the cycle preceting the Inspection that Is the subject of the repor.I. The aluMl accident induced leakage rate from the portion of the tubes below 18.1 Inchxem fom the top of the tubesheet for the most limiting accident in the most lmiting SG. In addition, If the calculated accident induced lakap rate from the most imitng ascldent is les than 1.87 times the maximum operational primary to secondary lakag rate. the report should describe how it was determined, and H SE Unit No. 2 5.0-28 Amerximent No.