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Category:Letter
MONTHYEARAEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 ML24159A2522024-05-30030 May 2024 10 CFR 50.71(e) Update and Related Site Change Reports AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report 05000316/LER-2024-001, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARAEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-11, Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation2024-02-27027 February 2024 Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation AEP-NRC-2022-03, Final Supplemental Response to NRC Generic Letter 2004-022022-01-20020 January 2022 Final Supplemental Response to NRC Generic Letter 2004-02 AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation2021-12-16016 December 2021 Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation AEP-NRC-2021-43, Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval2021-07-21021 July 2021 Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval AEP-NRC-2021-16, Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval2021-02-25025 February 2021 Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval AEP-NRC-2021-18, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2021-02-18018 February 2021 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2020-50, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-07-0909 July 2020 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic2019-11-0404 November 2019 Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic AEP-NRC-2019-32, Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 22019-08-22022 August 2019 Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 2 AEP-NRC-2019-40, Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 02019-07-30030 July 2019 Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 0 AEP-NRC-2018-81, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-11-27027 November 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping AEP-NRC-2018-82, Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination2018-11-20020 November 2018 Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination AEP-NRC-2018-64, Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-09-27027 September 2018 Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML18334A2722018-09-18018 September 2018 LTR-SDA-II-18-41-NP, Revision 1, Responses to NRC Questions on the Expanded Scope Leak-Before-Break Evaluations for D.C. Cook, Units 1 and 2. AEP-NRC-2018-45, Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report2018-08-0909 August 2018 Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report AEP-NRC-2018-01, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-25025 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 AEP-NRC-2018-23, Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan2018-04-11011 April 2018 Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan ML18092A0842018-03-28028 March 2018 Donald C. Cook Nuclear Plant Unit 2, Response to Request for Additional Information Regarding Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program ML17346A7662017-12-0808 December 2017 Enclosures 2 & 3 to AEP-NRC-2017-56 - Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels and EAL Technical Basis Manual AEP-NRC-2017-56, Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels2017-12-0808 December 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels AEP-NRC-2017-30, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations2017-05-26026 May 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations AEP-NRC-2017-16, Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding2017-05-11011 May 2017 Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding AEP-NRC-2017-09, Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program2017-02-27027 February 2017 Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program AEP-NRC-2016-81, Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ...2016-11-0303 November 2016 Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ... AEP-NRC-2016-80, Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-10-31031 October 2016 Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools AEP-NRC-2016-79, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-10-12012 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident AEP-NRC-2016-69, Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force.2016-09-0909 September 2016 Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force. AEP-NRC-2016-56, Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-07-12012 July 2016 Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-54, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 582016-06-16016 June 2016 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 58 AEP-NRC-2016-48, Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control...2016-06-16016 June 2016 Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control... ML16169A1152016-05-0606 May 2016 Donald C. Cook Nuclear Plant Units 1 and 2 - Response to Sixth Request for Additional Information the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-24, Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-02-19019 February 2016 Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-14, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2016-01-21021 January 2016 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation AEP-NRC-2015-11, Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-12-17017 December 2015 Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term ML15323A4332015-11-16016 November 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions. ML15323A4342015-11-16016 November 2015 Response (Part 1) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-99, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.152015-10-30030 October 2015 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.15 AEP-NRC-2015-98, Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-10-30030 October 2015 Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-86, Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions.2015-09-18018 September 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions. AEP-NRC-2015-80, Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-28028 August 2015 Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-75, Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-24024 August 2015 Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-88, Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements2015-08-24024 August 2015 Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements AEP-NRC-2015-69, Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-08-0606 August 2015 Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15223A4362015-07-28028 July 2015 PWROG-15066-NP, Revision 0, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program. AEP-NRC-2015-63, Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection2015-07-17017 July 2015 Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection AEP-NRC-2015-64, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-07-17017 July 2015 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term 2024-08-15
[Table view] |
Text
U.S. NUCLEAR REGULATORY COM"'ON DOCKET NUMBER
,,NRC FoRM. 195
'2-76 I eS - 815 ILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL' DATE OF DOCUMENT Indiana & Michigan Pwri Co 11/7/77 Mr. Edson Ge Case New'York, N. Y.
DATE RECEIVED John Tillinghast 11/14/77 ETT CINOTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED ORIGINAL eQKI N C LASS I F I E D QCOPY DESCRIPTION +Io'. 440 $ QO ~g 7 /PE ENCLOSU RE
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Notorized 11/7/77 ~ ~ itrans the following: Consists of response to requested infoi in the form of a document entitled "Di Ci Cook Unit Noi 1 Reactor Vessel Material Surveillance Program" ~~~ ~~
DISTRIBUTION FOR i~mATERIAL ON REACTOR VESSEL DATA PER R. INGRAM 5-26-77 PLANT NAIIE:.. Cook Unit Noi 1. e R JL 11/14/77 (2-P)
FOR ACTION/INFORMATION a awfu.I ergo SAFETY BRANCH CHIEF:
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ZNETZIG INTERNAL DISTRIBUTION CPR I IIPC PANLICKI EISENHUT BUTLER GRIMES HAZELTON HOGE R. GLIB LE RANDALL EXTERNAL DISTRIBUTION CONTROL NUMBER
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INDIANA II MICHIGAN POlhIER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 November 7, 1977 Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 DPR No. 58 NOV >@9+- io Mr. Edson G. Case, Acting Director llA+~o~gs pN Office of Nuclear Reactor Regulation tueIII @@em U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Case:
This letter responds to Mr. Don K. Davis'etter of May 20, 1977 requesting reactor vessel material property information for the Donald C. Cook Nuclear Plant. Xn our letter dated July 25, 1977, we informed you that we would need additional time to provide the requested information.
Enclosed herewith are three (3) copies of a document entitled, "D. C. Cook Unit No. 1 Reactor Vessel Material Surveillance Program" which supplies the information requested.
Very truly yours, Vice'resident JT:mam Sworn and subscribed to before me on this 7 day of November 1977
' .in. New York County, New York V
r 773180132 Notary lic GREGORY M. GURICAII Hew York Notary Public, State of No, 31-4643431 Llualifier'I In New York County Commtjjfon Expires March 30,
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f l I g D. C. COOK UNIT NO. 1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluence (E > 1 Mev) at the inner surface of the reactor vessel as of March 31, 1977 is 8.38 x 10 n/cm~.
2.) The effective full power years (EFPY) of operation accumulated as of March 31, 1977 is 1.34 EFPY.
3.) Fabrication of the reactor vessel was performed by Combustion Engineering, Inc.
4.) a.) Sketch of the reactor vessel showing materials in the beltline region
=-is shown in Figure l. I b.) Information on each of the welds in the beltline region is shown in Tables 1 through 4.
c.) Information on each of the plates in the beltline region is shown in Tables 4 through 8.
5.) Information relative to the weld and plate material in the material surveillance program is shown in Tables 1 through 3 and 5 through 8.
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~ fi FIGURE 1 IDENTIFICATION AND LOCATION OF D. C. COOK UNIT NO. 1 REACTOR VESSEL BELTLIHE REGION HELD AND PLATE MATERIAL 90
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e TABLE 1 IDENTIFICATION AND LOCATION OF D. C. COOK UNIT NO. 1 VESSEL BELTLINE REGION'WELD METAL Wel d
. Wel d Wire Flux id i i ~Wlii P Control No. ~Te Heat No. ~Te Lot No. Post-Meld Heat Treatment Nozzle Shell Submerged Arc Ml.14 .. B-4 Mod. 13253 Linde 1092 3?91 . 1125-1175'F-40HR-FC Vertical Seams (Tandem Wire) B-4 Mod. '12008 1-442 A, B & C Nozzl e Shel 1 to Submerged Arc M1.18 B-4 Mod. 20291 Linde 1092 3833 1125-1175'F-40HR-FC Inter Shell Circle Seam 8-442 Inter. Shell Submerged Arc Ml.14 -
B-4 Mod. 13253 Linde 1092 3791 1125-1175'F-40HR-FC Vertical Seams (Tandem Mire) B-4 Mod. 12008 2-442 A, B & C Inter. to Lower Submerged Arc Ml .42 B-4 Mod. IP3571 Linde 1092 3958- 1125-1175'F-40HR-FC Shell Circle Seam 9-442 Lower Shell Submerged Arc M1.14- . B-4 Mod. 13253 Linde 1092 3791 1125-1175'F-40HR-FO Vertical Seams (Tandem Wire) B-4 Mod. 12008 3-442 A, B & C 4 Surveillance Submerged Arc 8-4 Mod. 13253 Linde 1092 3791 1125-1175'F-40HR-FC Wel d
TABLE 2 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION WELD METAL Meld Hire Flux Mei ht Percent T~e Heat No. ~Te Lot No. C fIn P Si Ni Mo Cr Cu V B4 Mod. 13253 Linde 1092 3791 .15 1.83 .013 .015 .06 .72 .45 .04 .07 B4 Mod. 12008 Linde 1092 3791 ..13 1.92 .01 0 .015 .05 .99 . .51 .06 .13 B4 ttod. 20291 Linde 1092 3833 .16 1.92 .008 .009 .03 .74 .51 B4 iMod. IP3571 Linde 1092 3958 .12 1.38 .017 .009 .21 .82 .54 -- .40 Surveillance Held .26 1. 33 . 023 .014 ,18 .74 .44 .02 .27. .00! '-
- Wire Analysis - No As Deposited Meld Analysis was Performed TABLE 3 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION MELD METAL Meld. Wire Flux Energy 100F RTNDT Shel f Energy Tvpe Heat No. ~Te Lot No.
TNDT
'F Ft-Lbs oF Ft-Lbs 'SI YS UTS KSI Elong.
B4 Nod. 13253 Linde 1092 3791 0* 84,74,70 0* 63.3 80.1 27.5 69.7 B4 Nod. 12008 B4 trod. 20291 Linde 1092 3833 0* 35,50,48 0* 70. 5 88.0 25.5 67.1 B4 Nod. IP3571 Linde 1092 3958 0* 40,46,46 0* 69.0 84.0 28.0 69.4 Surveillance Meld CE Tests -70 54,54,73 -56 115.5 Surveillance Meld W Tests 83,84,92 -70 111 67.1 81.9 26.8 69.2 Estimated per NRC Standard Review Plan Section 5.3.2
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TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT VESSEL INNER WALL LOCATIONS Plate or Fluence Plate or Weld Seam Location Seam No. NiCM~
Nozzle Shell Vertical Seam 1-442A 2.4 x 10 3.9 x 1017 II II 1-4428 II II 1-442C 4' x 10 Nozzle Shell to Inter. Shell Circle Seam 8-442 7.3 x 1017 Inter. Shell Vertical Seam 2-442A 6.2 x 1018 2-4428 1.1 x 1019 II fl 2-442C 1.1 x 1019 Inter. Shell to Lower Shell Circle Seam 9-442 2.0 x 1019 Lower Shell II II Vertical Seam 3-442A 1.1 x 1019 3-4428 6.2 x 1018 3-442C 1.1 x 1019 Nozzle Shell Plate 84405-1 7.3 x 10'?
84405-2 7.3 x 101>T II II 84405-3 7.3 x 101 Inter. Shell Plate 84406-1 2.0 x 1019 84406-2 2.0 x 1019 84406-3 2.0 x 1019 Lower Shell Plate 84407-1 2.0 x 10 84407-2 2.0 x 10199 84407-3 2.0 x 10
e e
TABLE 5
. IDENTIFICATION AND LOCATION OF VESSEL. BELTLINE REGION PLATE MATERIAL Mat'l. Heat Treatment
~Com onent Plate No. Heat No. ~Sec. No. ~Su 1 Ter Austenitize ~Tem er Stress Relief Nozzle Shell 84405-1 C3594 A5338 Cl. 1 Lukens 1600'F+50'F-4HR-Mg 1225'F+25'F-4HR-AC )150'F+25 F-40HR-FC II II.
II II 84405-2 C3594 A5338 Cl. 1 Lukens II II II 84405-3 C3872 A5338 Cl. 1 Lukens Inter. Shell 84406-1 C1260 A5338 Cl. 1 -Lukens 84406-2 C3506, A5338 Cl. 1 Lukens 84406-3* C3506 A5338 Cl. 1 Lukens Lower Shell 84407-1 C3929 A5338 Cl. 1 Lukens II II 84407-2 C3932 A5538 Cl. 1 Lukens 84407-3. C3929 A5538 Cl. 1 Lukens
- Surveillance Material same as Inter. Shell Plate 84406-3 TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION PLATE MATERIAL Mei ht Percent Plate No. Mn S Si Ni Mo 84405-1 '21 1.42 .007 .018 .26 , .46 .47 .14 84405-2 . .20 1.41 .006 .018 .25 .45 .47 ..14 84405-3 .24 1.30 .008 .013 .30 .48 .46' l4 84406-1 .25 1.17 .01 6 .025 .29 .52 .49 - .12 84406-2 .24 1.41 .008 -
.015 .28 .50 .47 .15 84406-3 .21 1.40 .009 .015 .25 .49 .46 .15 84407-1 .21 1.35 .010 .014 .29 .55 .53 .14 8440?-2 .20 1.25 .012 .014 .22 .59 .54 .12 84407-3 .22 1.32 .010 .014 .24 .50 .55 .14 84406-3* .24 1.40 .009 .015 .25 .49 .46 .14
- Surveillance Plate Analysis Performed by Westi nghouse
~ M PL
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TABLE 7 Iv' MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION PLATE MATERIAL
~ii if E TNDT NOT* Ft-Lbs YS UTS El ong.
Plate No. oF OF MWD NMWD* KSI KSI I
B4405-1 10 2 134 87, 56.3 81.3 29.5 68.1 B4405-2 0 34 142 92 62.9 85.8 28.5 66.8 B4405-3 0 40 123.5 .
80 64.4 -'6.4 25.5 66.5 B4406-1 -10 - 8 123 80 63.3 86.3 27.0 67.1
-10 124, B4406-2 B4406-3 B4407-1
-10
-20 17 27 5
121 133 80.5 78.5 85.5 67.2 66.8 64.1 89.7 88.8 86.7 26.2 26.2 28.0 68.0 68.0 69.6
~
B4407-2 -20 -15 149 97 62.1 84.1 27.2 70.6 B4407-3 0 0 139 90;5 63.7 86.4 27.2 69.7
- Estimated from Data in the Major Working Direction (MWD) per NRC Standard Review Plan Se'ction 5.3.2 TABLE 8 MECHANICAL PROPERTIES OF SURVEILLANCE PLATE 5 OTHER BELTLINE PLATES PERFORMED BY WESTINGHOUSE Shelf Ener NDT RTND1 Ft-L s YS UTS Elong.
Plate 'No. oP oF MWD NMWD KSI KSI B4406-1 5 83 B4406-2 33 96 B4406-3 40 130 98 68 ' 90.4 27.5 70. 0 B4407-1 28 103 B4407-2 -12 126 B4407-3 38 108