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Category:Letter
MONTHYEARIR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion AEP-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-2024-76, 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 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 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 ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 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 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 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 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 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 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 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report 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 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] |
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DES C BI PT I ON ENCLOSU BE srs~c4'tr, notorized 4/22/77 ~ ~ ~ .trans the-following: Consists of requested information regar'ding the chemical cleaqing'of, the .Unit No..2
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INDIANA II MICHIGAN POWER COMPANY P. O. BOX 18 BO WL IN G G R E EN STAT ION NEW YORK, N. Y. 10004 April 22, 1977 Donald C. Cook Nuclear plant Unit No. 1 Docket No. 50-315 I 'i/ 8 DPR No. 58 Reggatory,P jig Cy, egg(~> ~
<PRZ8 pp, Mr. Benard Rusche, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 IT j~~
Dear Mr. Rusche:
This letter provides information requested by Mr. M. H. Fletcher, of the NRC Division of Operating Reactors, in connection with our letter of March 16, 1977 to you con-cerning the chemical cleaning of the Unit No. 2 Feedwater and Condensate Systems. His requests and our responses follow.
Provide a detailed description of the chemical cleaning operation which indicates how a ph of 9.0 is expected in the absorption field following the discharge of the cleaning solution.
~Res onse The 300,000 gallons of flushing solution (pH approximately 11.4) will be displaced through the turbine room sump (capacity 90,000 gallons) to the absorption field. It will be continuously pumped by the sump pumps at. a rate of 2,000 to 3,000 plus gpm.
The displacement rinses of demineralized water (pH about 6.5 to 7.5) will follow. These will also be continuously pumped to the field. Total rinse volume will be about 600,000 gallons.
The solution and displacement rinses will mix with the approximately 2 x 10 gallons in the absorption field, with a resultant pH of around 10.5. Subsequent discharge of waste water from the turbine room sump (approximately 300,000 gallons/day, pH about 6.5 to 7.5) will further lower the pH to 9.0 or less in two 7'//7o gad
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Mr. B. C. Rusche April 22, 1977 to four weeks. The sediment on the bottom of the pond will assist in lowering the pH.
The ability of the waste water to reduce the pH to 9.0 has been confirmed by a rough titration of a sample of the flush/
rinse solution with a sample of waste water now in the absorption field. This showed that, about 7 to 8 x 106 gallons of "normal" waste water would reduce the pH from about 11.4 to 9.0..
Based on the above operations and characteristics of the rinse water, "normal" waste water, and the absorption field sediment, it is our considered engineering judgement that the resultant water which eventually percolates into the ground will have a pH of 9.0 or less and would therefore meet the intent of the technical specifications with xespect to pH limitations.
- 2. The letter of March 16, 1977 requested that the licensee not be required to monitor the discharge to the absorption pond for heavy metals other than iron and copper since the systems being chemically cleaned are made up almost entirely of iron and copper. Since Appendix B Section 2.2.3.2, which requires the monitoring of heavy metals, is intended specifically for the type chemical cleaning operation proposed, provide justification for the request.
~Res onse The Peedwater and Condensate Systems in Unit 2 of the Donald C. Cook Nuclear plant are made only of carbon steel, stain-less steel and copper. The carbon steel has some rust deposits which would be removed by the cleaning operation resulting quantities of iron being discharged with the cleaning in'mall solution. Copper exhibits a very slow corrosion zate in a basic solution such as that which will be used in the subject. chemical cleaning operation. Even the very large surface area represented by the copper tubing in the condensers should, when cleaned, result in just barely measurable quantities of copper being discharged with the cleaning solution.
Stainless steel is particularly resistant to corrosion such that no rust exists on the stainless steel surfaces and no corrosion will xesult from contact with the cleaning solution.
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Mr. B. C. Rusche April 22, 1977 Appendix B Specification 2,.2.3.2 requires monitoring for heavy metals when spent chemical cleaning solutions are to be discharged to the absorption field. We will comply with this by monitoring for those potential candidates which could be removed by the cleaning 'operation - iron and copper.
- 3. Provide an appraisal of the environmental impact resulting from the discharge of the chemical cleaning solution and flush waters to the absorption field. Include any supportive information which is available.
~Res onse The Technical Specifications require that all chemical discharges to the absorption field be neutralized to give a pH in the range of 5.5 to 9 prior to discharge. For purposes of
=this one-time chemical cleaning operation our request amounts to neutralization of the discharge in the pond water after discharge, rather than neutralization in the plant prior to discharge.
A similar chemical cleaning operation for Unit 1 was performed in July 1973. Preoperational terrestrial and aquatic studies were in effect at that time and, although no separate observations were made specifically for this event, no damage to the flora and fauna around the absorption field or to the aquatic life was detected. (See Appendix D, "Terrestrial Studies" in the Environmental Operating Report (EOR) covering October through December 1974, and Benton Harbor Power Plant Limnological Studies, Special Report No. 44 .of the Great Lakes Research Division of the University of Michigan. In addition, the postoperational studies now in effect, have detected no changes of a long term nature which are attributable to the first cleaning. (See EOR's covering all of 1975 and. 1976).
Groundwater monitoring at the site, as required by Appendix B Technical Specification 4.1.1.5, was started in late 1974, slightly over one year following the first cleaning operation. Two wells were drilled from which groundwater moving from the absorption pond to the lake can be monitored. Sampling from these has shown that even when high discharge quantities are sent to the absorption, pond, (averaging 300,000 gallons/day with pH varying between 5.5 and 9.0 since restart of construction activities in Unit 2 in 1975), the pH of the groundwater does not vary to any significant degree (7.0 to 7.8 in the last two years).
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Per. B. C. Rusche April 22, 1977 The discharge of the chemical cleaning solution and flush waters to the absorption field resulting from the cleaning of the Unit 2 Feedwater and Condensate Systems at the Donald C. Cook Nuclear Plant will have a negligible environmental impact in and around the vicinity of the absorption field.
Very truly yours, Vice President JT:mam Sworn and subscribed to before me this 22nd day of April, 1977 in New York County, New York Notary Public KATI.HHPA DARRX NOTARY PUSt.!C, State ol New York, Yo. 41-4GOG793'"
Qualitied in Queens County County.
g~tjIicate liled irt New York 19'Ff Cornnusston axpuus triarch 30, cc: G. Charnoff P. W. Steketee R. C. Callen R. Walsh R. J. Vollen R. W. Jurgensen Bridgman R. S. Hunter
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INDIANA R MICHIGAN POWER COMPANY P O. BOX 18 BOWLING GREEN STATION HRW YORK, N. Y. 1000i April 22, 1977 Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 DPR No. 58 Mr. Benard Rusche, Director Office of Nuclear Reactor Regulation U;S. Nuclear Regulatory Commission Whshington, D.C. 20555
Dear Mr. Rusche:
This letter provides information requested by Mr. M. H. Fletcher, of the NRC Division of Operating Reactors, in connection with our letter of March 16, 1977 to you con-cerning 'the chemical cleaning of the Unit No. 2 Feedwater and Condensate Systems. His requests and our responses follow.
- 1. Provide a detailed description of the chemical cleaning operation which indicates how a ph of 9.0 is expected in the absorption field following the discharge of the cleaning solution.
Res onse The 300,000 gallons of flushing solution (pH approximately
'1.4) will be displaced through the turbine room sump (capacity 90,000 gallons) to the absorption field.. It will be continuously pumped by the sump'pumps at a rate of 2,000 to 3,000 plus gpm.
The displacement rinses of demineralized water (pH about 6.5 to
'.5) will follow. These will also be continuously pumped to the field. Total. rinse volume will be about 600,000 gallons.
va ra and displacement rinses will mix with the
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The solution approximately 2 x 10 gallons in the absorption field, with a resultant pH of around 10.5. Subsequent discharge of waste water from the turbine room sump (approximately '300,000 gallons/day, pH about 6.5 to 7.5) will further lower the pH to 9.0 or less in two
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Mr. B. C. Rusche April 22, 1977 to four weeks. The sediment. on the bottom of the pond will assist in lowering the pH.
The ability of the waste water to reduce the pH to 9.0 has been confirmed by a rough titration of a sample of the flush/
rinse solution with a sample of waste water now in the absorption field. This showed that about 7 to 8 x 106 gallons of "normal" waste water would reduce the pH from about 11.4'to 9.0.
Based on the above operations and characteristics of the rinse water, "normal" waste water, and the absorption field sediment, it is our considered engineering judgement that the
'resultant water which eventually percolates into "the ground will have a pH of 9.0 or less and would therefore meet the intent of the technical specifications with respect to pH limitations.
- 2. The letter of March 16, 1977 requested that the
.licensee not be required to monitor the discharge to the absorption pond for heavy metals other than iron and copper since the systems being chemically cleaned are made up almost entirely of iron and copper. Since Appendix B Section 2.2.3.2, which requires the monitoring of heavy metals, is intended specifically for the type chemical cleaning operation II proposed, provide justification for the request.
~Res ense The Feedwater and Condensate Systems in Unit 2 of the
. Donald C. Cook, Nuc3.ear Plant are made only of carbon steel, stain-less steel and copper. The carbon steel has some rust deposits
-
which would be removed by the cleaning operation resulting in small quantities of iron being discharged with the cle'aning solution. Copper exhibits a very slow corrosion rate in a basic
. solution such as that which will be used, in the subject chemical cleaning operation. rien the very large surface area represented by the copper tubing in the condensers should, when cleaned, result in just barely measurable quantities= of copper being discharged with the cleaning solution.
,Stainless steel is particularly resistant to corrosion such that no rust exists on the stainless steel surfaces and no corrosion will result from contact with the cleaning solution.
gr. B. c. Rusche ~ ApM1. 22, 1977 Appendix B Specification 2.2.3.2 requires monitoring for heavy metals when spent chemical cleaning solutions are to be discharged to the absorption field. We will comply with this by monitoring for those potential candidates which could be removed by the cleaning operation - iron and copper.
- 3. Provide an appraisal of the environmental impact resulting from the discharge of the chemical cleaning solution and flush waters to the absorption field. Xnclude any supportive information which is available.
.Res onse The Technical Specifications require that all chemical discharges to the absorption field be neutralized to give a pH in the range of 5;5 to 9 prior to discharge. For purposes of this one-time chemical cleaning operation our request amounts to neutralization of the discharge in the pond water after discharge, rather than neutralization in the plant prior to discharge.
A similar chemical cleaning operation for Unit 1 was performed in July 1973. Preoperational terrestrial and aquatic studies were in effect at that time and,,although no separate observations were made specifically for this event, no damage to the flora and fauna around the absorption field or to the aquatic life was detected. (See Appendix D, "Terrestrial Studies" in the Environmental Operating Report (EOR) covering October
'hrough December 1974, and Benton Harbor Power Plant Limnological
~
Studies, Special Report No. 44 of the Great Lakes Research Division of the University of Michigan. Xn addition, the postoperational studies now in effect have detected no changes of a long term nature which are attributable to the first cleaning. (See EOR's covering all of 1975 and 1976).
Groundwater monitoring at the site, as required by Appendix B Technical Specification 4.1.1.5, 'was started. in late 1974, slightly over one year following the first cleaning operation. Two wells were drilled from. which groundwater moving from the absorption pond to the lake can. be, monitored. Sampling from these has show'n that. even when high. discharge quantities are sent to the absorption, pond, (averaging 300,000 gallons/day with pH varying between 5.5 and .9.0 since restart of construction activities in Unit 2 in 1975), the pH of the groundwater does not vary to any significant degree (7.0 to 7.8 in the last two years) .
S. C. Rusche April 22, 1977 The discharge of the chemical cleaning solution and flush waters to the absorption field resulting from the cleaning of the Unit 2 Feedwater and Condensate Systems at the Donald C.'Cook Nuclear Plant will have a negligible environmental impact in and around the vicinity of the absorption field.
Very truly yours, Vice President JT imam Sworn and subscribed to before me this 22nd day of April, 1977 in New York County, New York Notary Public KATEILEC".4 BARRY HOTARY irUitt.tC, Stets ot thew York No. 41-iGOG i&2 Qualified in Queens County Certificete filed in Hew 'lark Cornnussran tkprres lnerah 30'97
~ I cc: G. Charnoff P N. Steketee R. C. Callen R. Nalsh R., J. Vollen
, R. N. Jurgensen - Bridgman R. S. Hunter
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