Similar Documents at Cook |
---|
Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARAEP-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-2016-48, 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... 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 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-2015-98, 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 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 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-2015-88, 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-2015-75, 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-2015-69, 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-2015-64, 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 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-2015-60, Response to a Request for Additional Information Regarding the 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 3.8.1.152015-07-0909 July 2015 Response to a Request for Additional Information Regarding the 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-2015-66, Response to Request for Additional Information Regarding Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-07-0202 July 2015 Response to Request for Additional Information Regarding Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18219D0951978-09-29029 September 1978 D.C Cook - Acknowledges 07/12/1978 Letter Advising of Additional Information to Complete NRC Staff'S Review of D.C Cook Nuclear Plant'S Ice - Basket Stress Analysis ML18219D7991978-09-29029 September 1978 Response to Request for Additional Information on Ice Basket Stress Analysis, Prepared by Westinghouse Electric Corporation 2022-01-20
[Table view] |
Text
NPiC DIS BUTION FOR PART 50 DOCKET I'RIAL (TEMiPORARY FORM)
CONTROL NO:
FILE' ROM: Indiana 6 Mich. Power Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER New York, N.Y. 10004 5-23-75 5-27-75 XX TO: ORIG CC OTHER SENT AEC PDR XX Mr. K. Kniel 1 signed SENT LOCAL PDR 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 ENCLOSURES:
info re.potential'or occurrence & the poten ial consequences of secondary system fluid flow will be submitted by 7-15-75...
O,a" .""
O >g"<lpga,",~ih SiI,~>> c~,'-'
PLANT NAME Cook 1 6 2 FOR ACTION/INFORMATION DHL 5-29-75 BUTLER (L) SCHWENCER (L) ZIEMANN (L) BEGAN (E)
W/ Copies 'LV/ Copies W/ Copies W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L)
W/ Copies W/ Copies W/ Copies Wl Cooies i ~c'li ~ ~ l vHooRi LV t' h.!'ilG.i i vl" Ii:] epA l's*ep W/ Copies W/ Copies bY/ Copies W/ Copies DANIEL (L) PURPLE (L) YOUNGBLOOD (E) LICEilSING PROJECT MANAGER W opies W/Copies W/ Copies W/ Copies INTERNAL DISTRIBUTION EG FILE TECH REVIE'V DENTON LIC ASST A/T IND ~
2 SCHROEDER GR Ii4ES R. DIGGS (L) BRAITMAi~I OGC, ROOM P-506A MACCARY GAMMILL H. GEARIN (L) SALTZMiAN GOSSI CK/STAF F KNIGHT KASTNER E. GOULBOURNE (L) MELTZ CASE nAWLICKI BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANGLER J. LEE (L) PLANS BOYD STELLO M. MAIGRET (L) QVCDONALD MOORE (L) HOUSTON ENVI RO S. REED (E) CHAPiVIAN DEYOUNG (L) NOVAK nnuLLER An. sERvlcE (L) DUBF (Ltr)
SKQVHOLT (L) ROSS DICKER 5. SHEPPARD (L) E. COUPE GOLLER (L) (Ltr) IPPOLITO KNIGHTQN Al. SLATER (E) PETERSON P. COLLINS TEDESCO YOUNG 8 LOOD H. SMITH (L) HA RT F I E LD (2)
DENISE J. COLLINS BEGAN S. TEETS (L) KLECKER QEG OPR LAINAS PROJECT LDR G. \VI LLIAMS (E) EISENHUT VFILE & REGION ('~) BFNAROYA V. WILSON (L) ,Wl G G I N TON MPIC VOLLMER HAR LESS R. INGRAM (L)
STFF.LE EXTERNAL DISTRIBUTION LOCAL POR~cceephe, Mich.
1 TIC (ABERNATIRY) (1)(2)(10) NATIONAL LABS 1 P D R.SAN/LA/NY 1 NSIC (BUCI-IANAi"J) 1 4Y. PENNINGTON, Rm E-201 GT 1 BROOKHAVCN iIAT LAB 1 ASLB 1 CONSULTANTS 1 G. ULR IKSON, ORNiL
. c Newton Anderson NEWi11AR K/8 LUME/AGBA8 I AN 1 AGMED (RUTH GUSShIAN)
ACBS HOLDING/SENT 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 Ilygpt875. ~
<K~IC EliERCr C&llIsff8N Iy May 23, 1975 Docket No. - 50-316 DPR No'. 58~ C PR No. 61
>op u,'~<@~ s
++ 4>~ ~o Mr. Karl Kniel Chief Pressurizel Naker Reactors ~/pe Branch No. 2 Directorate of Licensing U.S. Nuclear"Regulatory Commission Washington, D.C'0555
Dear Mr. Kniel:
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, ce, i ghast President JT:ma cc: Gerald Charnoff Richard Walsh Peter W. Steketee Robert J. Vollen Richard C. Callen R. W. Jurgensen - Bridgman R. S. Hunter
~ ~ 4 '
~
C J T
~ ~
e ~
l NRC DIE 'BUTtON FOR PART 50 DOCKET TERIAL (TEMPORARY FORM)
CONTROL NQ: ~
Fll E:
FROM:American Electric Power Co DATE OF DOC DATE REC'D LTR TWX RPT New York; N.Y.
TO: ORIG CC OTHER SENT AEC PDR Karl Kniel 1 Signed SENT I OCAL PDR CLASS UNC LASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
xEooocx '1 50<<315 DESCRIPTION: ENC LOS U R ES:
Ltr ~ Re their ltr. of 4-14-75, advising of; schedule ~ ..concerning installation of additio al isolation valves. ~ ., ~ ~ ~ ~
( 1 cy. Ltr.'ec'd) r
~
PLANT NAME: Cook y 1 d FOR ACTION/INFOBf",IATION 5~31~75 BUTLER (L) SCHWENCER (L) ZIEMANN (L) REGAN (E)
W/ Copies W/ Copies W/ Copies W/ Copies CLARK (I.) STOI Z (L) DICKER (E) LEAR (L)
W/ Copies W/ Copies W/ Copies . W/ Cooies PAnn (
~
VASSALi O {i t K i' G H i Q [~e <> rr .i.>
r W/ Copies I NIEL (L)
W/ opies I I:
W/ Copies PURPLE (L)
W/. Copies TECH REVIEW W/ Copies YOUNG B LOOD (E)
W/ Copies INTERNAL DISTRIBUTION DENTON W/ Copies LIC""NBING PROJECT HANAGER W/ Copies LIC ASST A/T Ih!D .
.Nf<C SCHROEDER G R liviES R. DIGGS (L) BiRAITMAN ROOM P.606A
'QGC, MACCARY GAMMiI L L H. GEARIN (L) SA LTZiVIAN
, GQSSICK/STAFF KNIGHT KASTNE R E. GOULBOURNE (L) MELTZ CASE AWLICI'I BALLAR0 P, KREUTZER (E)
GIAMBUSSO SHAO SPANGLER J lEE (L)
~
PLANS I3OYD STELLO M. MAIGRET (L) CDQNALD MOORE (L) HOUS1 QN ENVIRO S. REEO (E) CHAPiViAN DEYOUNG (L) NOVAK rxuLLER M. SERVICi= (L) ~DUBE {L'.r)
SKQVHQLT (L) ROSS DICKER S. SHEPPARD (L) E. COUPE GOLLFR {L) (Lu) IPPO LI TQ KN I G I!TON M. SLATER (E) PETERSON f'. COLLINS TEDESCO YOUNG B LOQD H. S!ill1 H (L) HAR1FIF:l.O (2}
DENISE J . COLLlNS BEGAN S. TEETS (L) KLECKER BEG QPR LAINiAS PROJECT LDR G. bil LLIAi~:IS (F) EISENHUT I:-Ii:a=a REGION (8) BENAROYA V. WILSON (L) ,WIGG IN1 QN 1IPIC YOLLMER HAR LESS R. INGRAM (L)
STEELE E>;TL= NAI. OIS I R I!3UTION LOCAL PDR
~
~
1 1
'I TIC (ABERi ATH NSIC'(BUCI.IANAN)
(1 )(i0) NATIONAL LADS W PEf<NIi fGTQi Rnl E.201 GT 1
1 PD R-SAN/LA/NY BRQOKHAVEN;!ATLAB tS~
1 1 ASI.B 1 CONSULTANTS 1 G. ULRIKSQi'0, Q:iii l.
Neo ton And.rsorn Q NEWi11ARK BLUhrlE/AGDABIAN 1 AGME0 (fiUTH GUSSXIAi~!)
Rm 0-127 GT P <f ~ 1 J. D. RUNKLES, Rrn E 201 61
0 1 1,
r
~ I g Pp . r:
~ hw A
~
~ ~
C
~
'h
~ j ~ 0 g g t
0 A
J
>~r r p' I
~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
/I g Mr. Karl Kniel, Chief '~>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 them upstream of the existing valves. The remaining four fit can 'be located between the containment penetration and the existing air-operated valves. Currently we are pl ni-oagKKTED cl VSHRC MAY2 9 197~
gsa sos>ion i,
Qoc4t 04'~
> -'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.
4 V
, alM'
~ ~ p
\
n l
J f I
II J'
\
Q I 1 j
e
/
, 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
~ ~