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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
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NPiC DIS BUTION FOR PART 50 DOCKET I'RIAL (TEMiPORARY FORM)CONTROL NO: FILE'ROM: Indiana 6 Mich.Power Co New York, N.Y.10004 5-23-75 5-27-75 DATE OF DOC DATE REC'D LTR TWX RPT OTHER XX TO: Mr.K.Kniel ORIG 1 signed CC OTHER SENT AEC PDR SENT LOCAL PDR XX XX CLASS UNC LASS PROP INFO INPUT=NO CYS REC'D DOCKET NO: 0-31 16 Ltr re our 5-14-75 ltr...adv th info re.potential'or occurrence
&the poten consequences of secondary system fluid flow will be submitted by 7-15-75...
ENCLOSURES:
ial PLANT NAME Cook 1 6 2 O,a"."" O>g"<lpga,",~ih SiI,~>>c~,'-'FOR ACTION/INFORMATION DHL 5-29-75 BUTLER (L)W/Copies CLARK (L)W/Copies i~c'li~~l W/Copies DANIEL (L)W opies SCHWENCER (L)'LV/Copies STOLZ (L)W/Copies vHooRi LV t'W/Copies PURPLE (L)W/Copies ZIEMANN (L)W/Copies DICKER (E)W/Copies h.!'ilG.i i vl" Ii:]bY/Copies YOUNGBLOOD (E)W/Copies BEGAN (E)W/Copies LEAR (L)Wl Cooies epA l's*ep W/Copies LICEilSING PROJECT MANAGER W/Copies EG FILE 2 OGC, ROOM P-506A GOSSI CK/STAF F CASE GIAMBUSSO BOYD MOORE (L)DEYOUNG (L)SKQVHOLT (L)GOLLER (L)(Ltr)P.COLLINS DENISE QEG OPR VFILE®ION ('~)MPIC STFF.LE TECH REVIE'V SCHROEDER MACCARY KNIGHT nAWLICKI SHAO STELLO HOUSTON NOVAK ROSS IPPOLITO TEDESCO J.COLLINS LAI NAS BFNAROYA VOLLMER INTERNAL DISTRIBUTION DENTON GR Ii4ES GAMMI LL KASTNER BALLARD SPANGLER ENVI RO nnuLLER DICKER KNIG HTQN YOUNG 8 LOOD BEGAN PROJECT LDR HAR LESS LIC ASST R.DIGGS (L)H.GEARIN (L)E.GOULBOURNE (L)P.KREUTZER (E)J.LEE (L)M.MAIGRET (L)S.REED (E)An.sERvlcE (L)5.SHEPPARD (L)Al.SLATER (E)H.SMITH (L)S.TEETS (L)G.\VI LLIAMS (E)V.WILSON (L)R.INGRAM (L)EXTERNAL DISTRIBUTION A/T IND~BRAITMAi~I SALTZMiAN MELTZ PLANS QVCDONA LD CHAPiVIAN DUBF (Ltr)E.COUPE PETERSON HA RT F I E LD (2)KLECKER EISENHUT ,Wl G G I N TON-LOCAL POR~cceephe, Mich.1-TIC (ABERNATIRY)
(1)(2)(10)
-NATIONAL LABS 1-NSIC (BUCI-IANAi"J) 1-4Y.PENNINGTON, Rm E-201 GT 1-ASLB 1-CONSULTANTS
.c-Newton Anderson NEWi11AR K/8 LUME/AG BA8 I AN-ACBS HOLDING/SENT 1-P D R.SAN/LA/N Y 1 BROOKHAVCN iIAT LAB 1-G.ULR IKSON, ORNiL 1-AGMED (RUTH GUSShIAN)Rm 8-127 GT 1-J.D.RUNKLES, Rm E-201 GT Pl/C~0 1~~~~~~r~'r, y0gUl8tOPJ DocIIet QIL9 INDIANA IL MICHIGAN POWER COMPANY P.0, BOX 18 BOWLING GREEN STATION tIt'.NEW YORK, N.Y.10004 Ilyg pt875.~<K~IC EliERCr Iy C&llIsff8N May 23, 1975 Docket No.-50-316 DPR No'.58~C PR No.61 Mr.Karl Kniel Chief Pressurizel Naker Reactors Branch No.2 Directorate of Licensing U.S.Nuclear"Regulatory Commission Washington, D.C'0555
Dear Mr.Kniel:
>op u,'~<@~s++4>~~o~/pe Pursuant to the request in your letter to me of May 14, 1975, regarding information concerning the potential for occurrence and the potential consequences of secondary system fluid flow instability in the Donald C.Cook Nuclear Plant, please be advised that we will provide you with the subject information by July 15, 1975.Very truly yours, JT:ma i ghast ce, President cc: Gerald Charnoff Richard Walsh Peter W.Steketee Robert J.Vollen Richard C.Callen R.W.Jurgensen-Bridgman R.S.Hunter
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l NRC DIE'BUTtON FOR PART 50 DOCKETTERIAL (TEMPORARY FORM)CONTROL NQ:~Fll E: FROM:American Electric Power Co New York;N.Y.TO: Karl Kniel DATE OF DOC ORIG 1 Signed DATE REC'D LTR TWX RPT CC OTHER SENT AEC PDR SENT I OCAL PDR CLASS UNC LASS xEooocx PROP INFO INPUT NO CYS REC'D'1 DOCKET NO: 50<<315 DESCRIPTION:
Ltr~Re their ltr.of 4-14-75, advising of;schedule~..concerning installation of additio al isolation valves.~.,~~~~ENC LOS U R ES: (1 cy.Ltr.'ec'd) r~PLANT NAME: Cook y 1 FOR ACTION/INFOBf",IATION d 5~31~75 BUTLER (L)W/Copies CLARK (I.)W/Copies PAnn (~W/Copies r I NIEL (L)W/opies SCHWENCER (L)W/Copies STOI Z (L)W/Copies VASSALi O{i t W/Copies PURPLE (L)W/.Copies ZIEMANN (L)W/Copies DICKER (E)W/Copies K i'G H i Q[~e W/Copies YOUNG B LOOD W/Copies REGAN (E)W/Copies LEAR (L).W/Cooies<>rr.i.>W/Copies (E)LIC""NBING PROJECT HANAGER W/Copies I I:.Nf<C'QGC, ROOM P.606A , GQSSICK/STAFF CASE GIAMBUSSO I3OYD MOORE (L)DEYOUNG (L)SKQVHQLT (L)GOLLFR{L)(Lu)f'.COLLINS DENISE BEG QPR I:-Ii:a=a REGION (8)1IPIC STEELE TECH REVIEW SCHROEDER MACCARY KNIGHT AWLICI'I SHAO STELLO HOUS1 QN NOVAK ROSS IPPO LI TQ TEDESCO J.COLLlNS LAI NiAS BENAROYA YOLLME R DENTON G R liviES GAMMi I L L KASTNE R BALLAR0 SPANGLER R.H.E.P, J~M.ENVIRO S.rxuLLER M.DICKER S.KN I G I!TON M.YOUNG B LOQD H.BEGAN S.PROJECT LDR G.V.HAR LESS R.LIC ASST DIGGS (L)GEARIN (L)GOULBOURNE KREUTZER (E)lEE (L)MAIG RET (L)REEO (E)SERVICi=(L)SHEPPARD (L)SLATER (E)S!ill1 H (L)TEETS (L)bil LLI Ai~:IS (F)WILSON (L)INGRAM (L)INTERNAL DISTRIBUTION (L)A/T Ih!D.BiRAITMAN SA LTZiVI AN MELTZ PLANS CDQNALD CHAPiViAN~DUBE{L'.r)E.COUPE PETERSON HAR1FIF:l.O (2}KLECKER EISENHUT ,WIGG IN1 QN E>;TL=NAI.OIS I R I!3UTION 1-LOCAL PDR~1-TIC (ABERi ATH (1)(i0)-NATIONAL LADS~'I-NSIC'(BUCI.IANAN) 1 W PEf<NIi fGTQi Rnl E.201 GT 1-ASI.B 1-CONSULTANTS
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~See'"'~-AMERICAN EI ECYHIC POVfER Service Corporati oa 2 BroaChoay, Nno York, K Z 10004 (2/2)422.4800 Docket No.50-315 DPR No.58 May 22, 1975 Mr.Karl Kniel, Chief/I g'~>6a Pressurized ttlater Reactor Branch No.2 Directorate of Licensing U.S.Nuclear Regulatory Commission
'>lashington, D.C.20555
Dear Hr.Kniel-In a letter dated April 14,
1975', I informed you there is an inadequate number of containment isolation valves in the non-essential service water lines to the containment ventilation units at the Donald.C.Cook Nuclear Plant~Unit 1.tlat'e stated that our corrective action would be to ins~~al the additional isolation valves.Ne have subsequently discussed this with your Mr.Robert Benedict and this letter is in response to his request f'r a schedule for performing this work.Twenty additional valves are required-ten on inlet lines and ten on outlet lines.On each inlet line we will add.a check valve as the second isolation valve.This valve will be located in the pipe between the contain-ment penetration and the existing air-operated isolation valve.It will require a plant shutdown to add these check valves.On each outlet line we will add an air-operated valve.Six of these will be located.downstream of the existing air-operated isolation valves because there is no space to fit them upstream of the existing valves.The remaining four can'be located between the containment penetration and the existing air-operated valves.Currently we are pl ni-oagKKTED cl VSHRC MAY 2 9 197~gsa sos>ion Qoc4t 04'~>i,-'5865
~\~"I hh.Karl Kniel May 22, 1975 to install the six downstreamvalves before the next scheduled plant shutdown.But we will be unable to make these valves operable (e.g.connect them e3ectrically and supply them with control air)until the next outage.Me are presently locating these six valves on mechanical drawings, after which we will shut off the existing air-operated isolation valves, cut the pipe, and add the required spool piece and new valve.Xt is necessary that the cooling water to a containment ventila-tion unit be terminated while the additional valve is being installed.
We do not expect to incur problems with our containment cooling requirements.
Ue have scheduled the design work necessary for the additional air-operated valves to be completed before the next outage which is scheduled to start by about July l.Therefore, during the outage we would plan to install all the check valves, connect the six air-operated.
valves to their electrical and instrumentation terminals, and add.the four remaining air-operated valves and make their electrical and instrumentation connections.
Ve now have all the additional air-operated valvess<that are required..
Me have not yet been able to obtain the required carbon steel check valves but have located on site suitable stainless steel check valves which may be used in the event we can not get the carbon steel valves in time.Me are striving to have the additional isolation valve work completed and the valves made operational before restarting the unit in operation.
However our success depends on our ability to obtain the qualified welders to do this work.ln line with our quality assurance program, we have the proper documentation for the equipment on*hand.to be installed and we will adhere to the proper quality assurance requirements and procedures in performing this work.
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, Hr.Karl Kniel t3 May 22)1975 Should any difficulties arise>rhich necessitate a change in our plans rre>rill inform you.Very truly yours, JED: mla ohn E.Dolan Exe tive Vice President Engineering and Construction cc: Gerald Charnoff Richard Nalsh Robert Z.Vollen Robert C.Callen Peter'V.Steketee R.8.Hunter R.M.Zurgensen-Bridgman K.R.Baker-NRC Resident Inspector-Bridgman I~4~~