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| {{#Wiki_filter:~., P~>yy IIIIIIIW IIIIII IIII/f 8Ãl/III ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649 J LEON D, WHITE.JR.VICE PRESIDENT TELEPHONE ARE*CDDE TIS 546-2700 July 27, 1978 | | {{#Wiki_filter:~., P~ >yy IIIIIIIW IIIIII IIII/f8Ãl/III ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 J |
| | LEON D, WHITE. JR. TELEPHONE VICE PRESIDENT ARE* CDDE TIS 546-2700 July 27, 1978 Director of Nuclear Reactor Regulations Attention: Mr. Dennis L. Ziemann, Chief Operating Reactor Branch No. 2 U.S. Nuclear Regulatory Commission r~ |
| | Washington, DC 20555 Cw'I C'lr-t |
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| ==Subject:== | | ==Subject:== |
| Reactor Vessel Fabrication and Inspection Information R.E.Ginna Nuclear Power Plant Unit Docket No.50-244 | | Reactor Vessel Fabrication and rrP |
| | ) |
| | Inspection Information I I |
| | CTI Cn~D R. E. Ginna Nuclear Power Plant Unit No;,~l'> C=.W Docket No. 50-244 MC TT I |
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| ==Dear Mr.Ziemann:== | | ==Dear Mr. Ziemann:== |
| Director of Nuclear Reactor Regulations Attention:
| | E4 Enclosed herewith please find a copy of the fabrication and inspection information requested by Mr. K. G. Hoge of your staff. |
| Mr.Dennis L.Ziemann, Chief Operating Reactor Branch No.2 U.S.Nuclear Regulatory Commission Washington, DC 20555 t rrP I I No;,~l'>TT I E4 r~Cw'I C'lr-)CTI Cn~D C=.W MC Enclosed herewith please find a copy of the fabrication and inspection information requested by Mr.K.G.Hoge of your staff.The following information list the various inspection reports and their dates for your documentation. | | The following information list the various inspection reports and their dates for your documentation. |
| a)"Ultrasonic Inspection of Rochester Gas and Electric Cor-poration Nuclear Reactor";BaW Fabrication Contract 610-0110;BSW Report No.615;January 26, 1968.b)."Robert E.Ginna Nuclear Power Station Preoperational In-spection Report";SWRI Project 17-2376;Final Report;January 1972.c)d)"1971 Inservice Power Station";"1972 Inservice Power Station";Examination of the Robert E.Ginna Nuclear SWRI project 17-3074;July 1972.Examination of the Robert E.Ginna Nuclear SWRI project 17-3377;July 1972.e)"1974 Inservice Examination of Class 1 Components at the R.E.Ginna Nuclear Power Station";SWRI Project 17-3874;September 1974 f)"1975 Inservice Examination of Class 1 Components at the R.E.Ginna Nuclear Power Station";SWRI Project 17-4206;June 1975.We hope this information is helpful to your staff.Very truly yours, I,782120043 L.D.White, Jr.~-----
| | a) "Ultrasonic Inspection of Rochester Gas and Electric Cor-poration Nuclear Reactor"; BaW Fabrication Contract 610-0110; BSW Report No. 615; January 26, 1968. |
| Ginna Station Reactor Vessel Governing Specifications 1.The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III,"Rules for Construction of Nuclear Vessels." 1965 and applicable code cases for Class A vessels.Code Cases-U er Shell'ourse
| | b) . "Robert E. Ginna Nuclear Power Station Preoperational In-spection Report"; SWRI Project 17-2376; Final Report; January 1972. |
| -1332-1 Shell is fabricated of SA-336 manganese-molybdenum steel.Lower Head Rin-1332-1 Ring is fabricated of SA-336 maganese-molybdenum steel.2.3.The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section IX, Welding Qualifications, 1965.ASA B31.1, Code for Pressure Piping, Section VI, Chapter 3 (1955).Westinghouse Atomic Power Division Equipment Specification E-676206 except as ammended by.Westinghouse Electric Corporation, Atomic Power Division Contract No.54-Q-49758-BP dated November 15, 1965.5.The Babcock 6 Wilcox Company, Quality Control Department Specifications covering: Welding, Nondestructive Testing, Heat Treating, Cleaning and Testing.Nondestructive Examinations Performed on Vessel A manual Ultrasonic Examination was performed on the reactor vessel at the Ginna Power Station location on December 4 through December 9 and December 18 through 22, 1967.The examination was performed by representa-tives of Babcock and Wilcox Quality Control N.D.T.Section.This examina-tion was performed in accordance with the requirements specified by Westing-house Atomic Power Division.The closure head was examined at BGW Co., Mt.Vernon, Indiana Works on November 29 and 30, 1967.In August 1969, Southwest Research Institute was contracted to perform preservice nondestructive examination on selected components, including the reactor vessel at Ginna, prior to the system's startup.These examinations were performed to evaluate the overall structural integrity of the system and to provide baseline information for subsequent inservice examination comparisons. | | c) "1971 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3074; July 1972. |
| A mechanized ultrasonic technique was employed.The procedure and sensitivity requirements for the examination were derived from South-west's experience and are in accordance with Section III, Appendix IX of the ASME Code.
| | d) "1972 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3377; July 1972. |
| Vlr Jl~bVLNL'4
| | e) "1974 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-3874; September 1974 f) "1975 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-4206; June 1975. |
| &Ajar'jLlltkl LVLV aurjL'utah
| | We hope this information is helpful to your staff. |
| -tczAL July l'ithbbUKh VESSEL ROBERT E.GINNA NUCLEAR POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1967 BSM Closure head-from the cooling shroud to the flange radius Vessel Flange No Recordable Indications No Indications Vessel flange to upper shell weld No Recordable Indications Vessel upper shell to Intermediate shell weld Vessel Intermediate shell to lower shell weld 23 minor indications (less than 100%.reference level.)(Shearwave)
| | Very truly yours, I,782120043 L. D. White, Jr. ~----- |
| No Recordable Indications Vessel lower shell course above radial core supports 5 minor indications (less than 60$reference level.)(Shearwave) | | |
| Primary coolant nozzles No Recordable Indications Nozzle to nozzle shell cour'se welds (Safety injection nozzles)one indication (405 of ref.level)Noz B two indications (70Ãof ref.level)Noz A ua,xsvaav[vxv r mmxi~rax<vis auto'usa>-l<nil LVK i Kj;bbUKh Vj'bbr L ROBERT E.GINNA NUCLEAR POWER STATION DATE EXVfINATION AREA IDENTIFICATION RESULTS 1969 SwRI Vessel-to-Flange circumferential weld No Significant Indications Head to Flange circumferential weld No Si gni fi cant Indi cati ons Upper shell to intermediate shell circumferential weld No Indications Intermediate shell to lower shell circumferential weld No Indications Lower shell to ring forging circumferential weld No Indications Ring forging to lower head weld No Indications Primary nozzle to vessel welds Loop A-Inlet Loop A-Outlet No Indications No Indications Loop 8-Inlet No Indications Loop 8-Outlet No Indications Primary nozzles to safe end welds Loop A-Inlet Loop A-Outlet No Indications No Significant Indications
| | Ginna Station Reactor Vessel Governing Specifications |
| ~~Loop 8-Inlet No Indications Loop 8-Outlet No Significant Indications us lxmbUllil I'luviLnniivn oueuvuii-5~1 lute t'r LDDUkcl VLobf L ROBERT E.GINNA NUCLEAR POWER STATION DATE EE&HNATION AREA IDENTIFICATION RESULTS 1969 Primary nozzle high strain areas No Indications Closure head studs (48 studs)No Indications Closure head cladding 8-6" x 6" patches (PT)No Indications 1971 SwRI Head to Flange circumferential welds.No Indications Closure head studs (48 studs)No Indications Closure head nuts (48 nuts)No Indications 48 Ligament areas between flange stud holes No Indications Flange to Upper shell circumferential weld.No Indications 1972 SwRI Closure head studs (48 studs)No Indications Closure head nuts (48 nuts)No Indications ul lnAbul'ilL I'Mill'iniluil
| | : 1. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Vessels." |
| ~vrlrvwxl-a(Gtil Iud(i 5LboUM vkbaf 4 ROBERT E.GINNA NUCLEAk POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1974 SwRI Vessel to flange circumferential weld No Recordable Indications Head to flange circumferential weld No Recordable Indications Control rod drive penetrations (VT)No Indications Closure head studs (48 studs)No Recordable Indications Closure head nuts (48 nuts)No Recordable Indications Closure head washers (VT)(48 washers)No Indications Interior surfaces and internals and integrally-welded internal supports (VT)Vessel flange ligaments between each stud hole No Indications Closure head cladding (PT)2-6" x 6" patches No Indications 1975 SwRI Nozzle to vessel weld-Loop A-Outlet Insignificant Indications Nozzle inside radius section-.Loop A-Outlet No Recordable Indications Nozzle to safe end weld-Loop A-Outlet No Recordable Indications ULltCADUlV JL L'~'LLiVAL LVL>burumiCz-~u.ivK rheaauwr.Vsaoec ROBERT E.GINNA NUCLEAR POWER STATION DATE ERQ1INATION AREA IDENTIFICATION RESULTS 1975 SwRI Nozzle to vessel weld-Loop 8-Outlet Insignificant Indications Nozzle inside radius section-Loop 8-Outlet No Recordable Indications Nozzle to safe end weld-Loop 8-Outlet No Recordable Indications Safety injection nozzle to vessel weld Loop A Safety injection nozzle inside radius section-Loop A Safety injection nozzle to vessel weld-Loop 8 No Recordable Indications No Recordable Indications No Recordable Indications Safety injection nozzle inside radius section-Loop 8 Closure head studs (48 studs)No Recordable Indications No Recordable Indications Closure head nuts (48 nuts)No Recordable Indications Closure head washers (48 washers)(VT)No Recordable Indications ULlKASONLC hXAHLHAL J.UN SUE'1t'IAK>
| | 1965 and applicable code cases for Class A vessels. |
| -K~l'TOK k'KESSUKE VESSEL ROBERT E.GINNA NUCLEAR POWER STATION DATE E)URINATION AREA IDENTIFICATION RESULTS 1978 SwRI Vessel flange ligaments between threaded stud holes (1/3 of the ligaments examined)Head-to-flange circumferential weld.(1/3 of the length of weld examined)Closure head studs (16 studs)(UT,HT)No Recordable Indications No Recordable Indications Insignificant Indications Closure head nuts (16 nuts)(UT,NT)No Significant Indications Closure head washers (16 washers)(VT)No Recordable Indications Closure head cladding (2-6" x 6" patches examined)(PT,VT)No Recordable Indications}}
| | Code Cases U er Shell'ourse 1332-1 Shell is fabricated of SA-336 manganese-molybdenum steel. |
| | Lower Head Rin 1332-1 Ring is fabricated of SA-336 maganese-molybdenum steel. |
| | : 2. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section IX, Welding Qualifications, 1965. |
| | : 3. ASA B31.1, Code for Pressure Piping, Section VI, Chapter 3 (1955). |
| | Westinghouse Atomic Power Division Equipment Specification E-676206 except as ammended by .Westinghouse Electric Corporation, Atomic Power Division Contract No. 54-Q-49758-BP dated November 15, 1965. |
| | : 5. The Babcock 6 Wilcox Company, Quality Control Department Specifications covering: Welding, Nondestructive Testing, Heat Treating, Cleaning and Testing. |
| | Nondestructive Examinations Performed on Vessel A manual Ultrasonic Examination was performed on the reactor vessel at the Ginna Power Station location on December 4 through December 9 and December 18 through 22, 1967. The examination was performed by representa-tives of Babcock and Wilcox Quality Control N.D.T. Section. This examina-tion was performed in accordance with the requirements specified by Westing-house Atomic Power Division. |
| | The closure head was examined at BGW Co., Mt. Vernon, Indiana Works on November 29 and 30, 1967. |
| | In August 1969, Southwest Research Institute was contracted to perform preservice nondestructive examination on selected components, including the reactor vessel at Ginna, prior to the system's startup. These examinations were performed to evaluate the overall structural integrity of the system and to provide baseline information for subsequent inservice examination comparisons. A mechanized ultrasonic technique was employed. The procedure and sensitivity requirements for the examination were derived from South-west's experience and are in accordance with Section III, Appendix IX of the ASME Code. |
| | |
| | VlrJl~bVLNL'4 &Ajar'jLlltklLVLV aurjL'utah - tczAL July l'ithbbUKh VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1967 BSM Closure head - from the cooling shroud to the No Recordable Indications flange radius Vessel Flange No Indications Vessel flange to upper shell weld No Recordable Indications Vessel upper shell to Intermediate shell weld 23 minor indications (less than 100% . |
| | reference level.) (Shearwave) |
| | Vessel Intermediate shell to lower shell weld No Recordable Indications Vessel lower shell course above radial core supports 5 minor indications (less than 60$ |
| | reference level.) (Shearwave) |
| | Primary coolant nozzles No Recordable Indications Nozzle to nozzle shell cour'se welds one indication (405 of ref. level) Noz B (Safety injection nozzles) two indications (70Ã of ref. level) Noz A |
| | |
| | ua,xsvaav[vxv r mmxi~rax <vis auto'usa> l<nil LVK i Kj;bbUKh Vj'bbr L ROBERT E. GINNA NUCLEAR POWER STATION DATE EXVfINATION AREA IDENTIFICATION RESULTS 1969 SwRI Vessel-to-Flange circumferential weld No Significant Indications Head to Flange circumferential weld No Si gni ficant Indi cati ons Upper shell to intermediate shell circumferential weld No Indications Intermediate shell to lower shell circumferential weld No Indications Lower shell to ring forging No Indications circumferential weld Ring forging to lower head weld No Indications Primary nozzle to vessel welds No Indications Loop A - Inlet Loop A - Outlet No Indications Loop 8 - Inlet No Indications Loop 8 - Outlet No Indications Primary nozzles to safe end welds No Indications Loop A - Inlet Loop A Outlet No Significant Indications ~ ~ |
| | Loop 8 - Inlet No Indications Loop 8 - Outlet No Significant Indications |
| | |
| | us lxmbUllil I'luviLnniivn oueuvuii - 5~1 lute t'r LDDUkcl VLobf L ROBERT E. GINNA NUCLEAR POWER STATION DATE EE&HNATION AREA IDENTIFICATION RESULTS 1969 Primary nozzle high strain areas No Indications Closure head studs (48 studs) No Indications Closure head cladding 8 - 6" x 6" patches (PT) No Indications 1971 SwRI Head to Flange circumferential welds . No Indications Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications 48 Ligament areas between flange stud holes No Indications Flange to Upper shell circumferential weld. No Indications 1972 SwRI Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications |
| | |
| | ul lnAbul'ilL I'Mill'iniluil~vrlrvwxl a(Gtil Iud( i 5LboUM vkbaf 4 ROBERT E. GINNA NUCLEAk POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1974 SwRI Vessel to flange circumferential weld No Recordable Indications Head to flange circumferential weld No Recordable Indications Control rod drive penetrations (VT) No Indications Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (VT) (48 washers) No Indications Interior surfaces and internals and integrally-welded internal supports (VT) |
| | Vessel flange ligaments between each stud hole No Indications Closure head cladding (PT) 2 6" x 6" patches No Indications 1975 SwRI Nozzle to vessel weld Loop A - Outlet Insignificant Indications Nozzle inside radius section .Loop A - Outlet No Recordable Indications Nozzle to safe end weld - Loop A - Outlet No Recordable Indications |
| | |
| | ULltCADUlVJL L'~'LLiVALLVL> burumiCz ~u.ivK rheaauwr. Vsaoec ROBERT E. GINNA NUCLEAR POWER STATION DATE ERQ1INATION AREA IDENTIFICATION RESULTS 1975 SwRI Nozzle to vessel weld - Loop 8 - Outlet Insignificant Indications Nozzle inside radius section Loop 8 - Outlet No Recordable Indications Nozzle to safe end weld - Loop 8 - Outlet No Recordable Indications Safety injection nozzle to vessel weld No Recordable Indications Loop A Safety injection nozzle inside radius section- No Recordable Indications Loop A Safety injection nozzle to vessel weld Loop 8 No Recordable Indications Safety injection nozzle inside radius section- No Recordable Indications Loop 8 Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (48 washers) (VT) No Recordable Indications |
| | |
| | ULlKASONLC hXAHLHALJ.UN SUE'1t'IAK> K~l'TOK k'KESSUKE VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E)URINATION AREA IDENTIFICATION RESULTS 1978 SwRI Vessel flange ligaments between threaded stud holes No Recordable Indications (1/3 of the ligaments examined) |
| | Head-to-flange circumferential weld. No Recordable Indications (1/3 of the length of weld examined) |
| | Closure head studs (16 studs) (UT,HT) Insignificant Indications Closure head nuts (16 nuts) (UT,NT) No Significant Indications Closure head washers (16 washers) (VT) No Recordable Indications Closure head cladding (2 - 6" x 6" patches examined) No Recordable Indications (PT,VT)}} |
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E. Ginna Nuclear Power Plant, License Amendment Request to Modify the Steam Generator Tube Inspection Frequency RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 ML20248H3882020-09-0404 September 2020 Response to Request for Additional Information - License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System. ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20080N8892020-03-20020 March 2020 R. E. Ginna Nuclear Power Plant, Supplemental Information Associated with the License Amendment Request to Add a One-Time Note for Use of Alternate Residual Heat Removal Methods JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18338A2352018-12-0404 December 2018 R. E. Ginna Nuclear Power Plant - Relief Request ISI-18 to Extend the Reactor Pressure Vessel Inservice Inspection Interval ML18243A1672018-08-29029 August 2018 R. E. Ginna Nuclear Power Plant - Response to Request for Additional Information - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Posit NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. ML17298B4442017-10-25025 October 2017 License Amendment Request - Revised Commitment Associated with Implementation of NFPA 805, 2001 Edition RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML16336A0482016-11-30030 November 2016 Response to Request for Additional Information for the Review of TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16042A4212016-02-11011 February 2016 Response to Request for Additional Information Regarding Reactor Internals Program ML16034A1392016-02-0303 February 2016 Response to Request for Additional Information - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program.. RS-15-288, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-12-0404 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-15-255, Response to NRC Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2015-09-30030 September 2015 Response to NRC Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report ML18143A4481978-07-28028 July 1978 R. E. Ginna - Response to Letter of 6/21/1978. Additional Information About Standby Auxiliary Feedwater System Attached ML18190A1671978-07-27027 July 1978 R. E. Ginna - Enclosed Copy of Reactor Vessel Fabrication & Inspection Information Requested by Mr. K. G. Hoge. Listed Various Inspection Reports & Dates for Documentation ML18142A6941978-06-15015 June 1978 Steam Generator Water Hammer Prevention ML18143A0291978-04-25025 April 1978 R. E. Ginna - Response to NRC Request Regarding Submittals of 01/16/1978 & 02/15/1978 on the ECCS Analyses for R. E. Ginna Nuclear Power Plant ML18142A7061978-04-0606 April 1978 Forwarding Revision to Tests Described in Applicant'S 03/27/78 Submittal Questions 6.1.E & 6.1.0 Re the Cycle 8 Fuel Reload ML18142B9741978-02-15015 February 1978 R. E. Ginna - 02/15/1978 Response to Request for Additional Information on Adequacy of ECCS Evaluation Model ML18142A8041978-01-18018 January 1978 R. E. Ginna - Enclosed Is Response to Nrc'S Questionnaire of 12/15/1977 Regarding Standby Diesel Generating Units ML18142B9751977-10-31031 October 1977 R. E. Ginna - 10/31/1977 Response to Request for Additional Information Inservice Pump and Valve Testing Program ML18142A8641977-09-13013 September 1977 R. E. Ginna - Response to Request of May 23, 1977 for Additional Information on the Ginna Reactor Vessel Material Surveillance Program ML18142A7191977-08-0404 August 1977 R. E. Ginna - 08/04/1977 Letter Response to Request for Additional Information on Inservice Pump and Valve Testing Program ML18142A8331977-02-24024 February 1977 R. E. Ginna - Fission Gas Release Model ML18142B9771977-02-24024 February 1977 R. E. Ginna - 02/24/1977 Response to Request for Additional Information Reactor Vessel Overpressurization ML18142A8371977-01-19019 January 1977 Forwards Response Letter of 12/17/1976 Requesting Additional Information Regarding Appendix I Evaluation ML18143A9671976-03-23023 March 1976 R. E. Ginna - Plans for Demonstrating Compliance with 10 CFR 50.34a 2024-08-09
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~., P~ >yy IIIIIIIW IIIIII IIII/f8Ãl/III ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 J
LEON D, WHITE. JR. TELEPHONE VICE PRESIDENT ARE* CDDE TIS 546-2700 July 27, 1978 Director of Nuclear Reactor Regulations Attention: Mr. Dennis L. Ziemann, Chief Operating Reactor Branch No. 2 U.S. Nuclear Regulatory Commission r~
Washington, DC 20555 Cw'I C'lr-t
Subject:
Reactor Vessel Fabrication and rrP
)
Inspection Information I I
CTI Cn~D R. E. Ginna Nuclear Power Plant Unit No;,~l'> C=.W Docket No. 50-244 MC TT I
Dear Mr. Ziemann:
E4 Enclosed herewith please find a copy of the fabrication and inspection information requested by Mr. K. G. Hoge of your staff.
The following information list the various inspection reports and their dates for your documentation.
a) "Ultrasonic Inspection of Rochester Gas and Electric Cor-poration Nuclear Reactor"; BaW Fabrication Contract 610-0110; BSW Report No. 615; January 26, 1968.
b) . "Robert E. Ginna Nuclear Power Station Preoperational In-spection Report"; SWRI Project 17-2376; Final Report; January 1972.
c) "1971 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3074; July 1972.
d) "1972 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3377; July 1972.
e) "1974 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-3874; September 1974 f) "1975 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-4206; June 1975.
We hope this information is helpful to your staff.
Very truly yours, I,782120043 L. D. White, Jr. ~-----
Ginna Station Reactor Vessel Governing Specifications
- 1. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Vessels."
1965 and applicable code cases for Class A vessels.
Code Cases U er Shell'ourse 1332-1 Shell is fabricated of SA-336 manganese-molybdenum steel.
Lower Head Rin 1332-1 Ring is fabricated of SA-336 maganese-molybdenum steel.
- 2. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section IX, Welding Qualifications, 1965.
- 3. ASA B31.1, Code for Pressure Piping,Section VI, Chapter 3 (1955).
Westinghouse Atomic Power Division Equipment Specification E-676206 except as ammended by .Westinghouse Electric Corporation, Atomic Power Division Contract No. 54-Q-49758-BP dated November 15, 1965.
- 5. The Babcock 6 Wilcox Company, Quality Control Department Specifications covering: Welding, Nondestructive Testing, Heat Treating, Cleaning and Testing.
Nondestructive Examinations Performed on Vessel A manual Ultrasonic Examination was performed on the reactor vessel at the Ginna Power Station location on December 4 through December 9 and December 18 through 22, 1967. The examination was performed by representa-tives of Babcock and Wilcox Quality Control N.D.T. Section. This examina-tion was performed in accordance with the requirements specified by Westing-house Atomic Power Division.
The closure head was examined at BGW Co., Mt. Vernon, Indiana Works on November 29 and 30, 1967.
In August 1969, Southwest Research Institute was contracted to perform preservice nondestructive examination on selected components, including the reactor vessel at Ginna, prior to the system's startup. These examinations were performed to evaluate the overall structural integrity of the system and to provide baseline information for subsequent inservice examination comparisons. A mechanized ultrasonic technique was employed. The procedure and sensitivity requirements for the examination were derived from South-west's experience and are in accordance with Section III, Appendix IX of the ASME Code.
VlrJl~bVLNL'4 &Ajar'jLlltklLVLV aurjL'utah - tczAL July l'ithbbUKh VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1967 BSM Closure head - from the cooling shroud to the No Recordable Indications flange radius Vessel Flange No Indications Vessel flange to upper shell weld No Recordable Indications Vessel upper shell to Intermediate shell weld 23 minor indications (less than 100% .
reference level.) (Shearwave)
Vessel Intermediate shell to lower shell weld No Recordable Indications Vessel lower shell course above radial core supports 5 minor indications (less than 60$
reference level.) (Shearwave)
Primary coolant nozzles No Recordable Indications Nozzle to nozzle shell cour'se welds one indication (405 of ref. level) Noz B (Safety injection nozzles) two indications (70Ã of ref. level) Noz A
ua,xsvaav[vxv r mmxi~rax <vis auto'usa> l<nil LVK i Kj;bbUKh Vj'bbr L ROBERT E. GINNA NUCLEAR POWER STATION DATE EXVfINATION AREA IDENTIFICATION RESULTS 1969 SwRI Vessel-to-Flange circumferential weld No Significant Indications Head to Flange circumferential weld No Si gni ficant Indi cati ons Upper shell to intermediate shell circumferential weld No Indications Intermediate shell to lower shell circumferential weld No Indications Lower shell to ring forging No Indications circumferential weld Ring forging to lower head weld No Indications Primary nozzle to vessel welds No Indications Loop A - Inlet Loop A - Outlet No Indications Loop 8 - Inlet No Indications Loop 8 - Outlet No Indications Primary nozzles to safe end welds No Indications Loop A - Inlet Loop A Outlet No Significant Indications ~ ~
Loop 8 - Inlet No Indications Loop 8 - Outlet No Significant Indications
us lxmbUllil I'luviLnniivn oueuvuii - 5~1 lute t'r LDDUkcl VLobf L ROBERT E. GINNA NUCLEAR POWER STATION DATE EE&HNATION AREA IDENTIFICATION RESULTS 1969 Primary nozzle high strain areas No Indications Closure head studs (48 studs) No Indications Closure head cladding 8 - 6" x 6" patches (PT) No Indications 1971 SwRI Head to Flange circumferential welds . No Indications Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications 48 Ligament areas between flange stud holes No Indications Flange to Upper shell circumferential weld. No Indications 1972 SwRI Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications
ul lnAbul'ilL I'Mill'iniluil~vrlrvwxl a(Gtil Iud( i 5LboUM vkbaf 4 ROBERT E. GINNA NUCLEAk POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1974 SwRI Vessel to flange circumferential weld No Recordable Indications Head to flange circumferential weld No Recordable Indications Control rod drive penetrations (VT) No Indications Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (VT) (48 washers) No Indications Interior surfaces and internals and integrally-welded internal supports (VT)
Vessel flange ligaments between each stud hole No Indications Closure head cladding (PT) 2 6" x 6" patches No Indications 1975 SwRI Nozzle to vessel weld Loop A - Outlet Insignificant Indications Nozzle inside radius section .Loop A - Outlet No Recordable Indications Nozzle to safe end weld - Loop A - Outlet No Recordable Indications
ULltCADUlVJL L'~'LLiVALLVL> burumiCz ~u.ivK rheaauwr. Vsaoec ROBERT E. GINNA NUCLEAR POWER STATION DATE ERQ1INATION AREA IDENTIFICATION RESULTS 1975 SwRI Nozzle to vessel weld - Loop 8 - Outlet Insignificant Indications Nozzle inside radius section Loop 8 - Outlet No Recordable Indications Nozzle to safe end weld - Loop 8 - Outlet No Recordable Indications Safety injection nozzle to vessel weld No Recordable Indications Loop A Safety injection nozzle inside radius section- No Recordable Indications Loop A Safety injection nozzle to vessel weld Loop 8 No Recordable Indications Safety injection nozzle inside radius section- No Recordable Indications Loop 8 Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (48 washers) (VT) No Recordable Indications
ULlKASONLC hXAHLHALJ.UN SUE'1t'IAK> K~l'TOK k'KESSUKE VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E)URINATION AREA IDENTIFICATION RESULTS 1978 SwRI Vessel flange ligaments between threaded stud holes No Recordable Indications (1/3 of the ligaments examined)
Head-to-flange circumferential weld. No Recordable Indications (1/3 of the length of weld examined)
Closure head studs (16 studs) (UT,HT) Insignificant Indications Closure head nuts (16 nuts) (UT,NT) No Significant Indications Closure head washers (16 washers) (VT) No Recordable Indications Closure head cladding (2 - 6" x 6" patches examined) No Recordable Indications (PT,VT)