Similar Documents at Cook |
---|
Category:Letter
MONTHYEARAEP-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, 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 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 AEP-NRC-2024-52, 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 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, 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 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 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 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 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09
[Table view] Category:Report
MONTHYEARML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report 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 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 ML22340A1762022-11-30030 November 2022 Commitment Change Summary October 2020 to May 2022 ML22340A1992022-11-30030 November 2022 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2) ML22340A2132022-11-30030 November 2022 R1900-0024-001, Revision 13, NFPA 805 Nuclear Safety Capability Assessment AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report ML21125A5582021-04-19019 April 2021 Report 2019, Commitment Change Summary, May 2019 to October 2020 ML21125A5392021-04-19019 April 2021 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2), Boration System Functionality Requirement Change in Mode 4 EA-21-024, Notice of Enforcement Discretion2021-03-0404 March 2021 Notice of Enforcement Discretion for Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level2021-01-28028 January 2021 Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level AEP-NRC-2020-28, CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations2020-05-0606 May 2020 CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations AEP-NRC-2020-23, Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2020-04-30030 April 2020 Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML20108E9992020-03-0505 March 2020 Enclosure 7 - LTR-SCS-19-50, Revision 0, D.C. Cook Unit 1 Low Temperature Overpressure Protection System (Ltops) Analysis for 48 EFPY, Dated March 5, 2020, Attachment 2 Only (Non-Proprietary) ML20108F0002020-02-28028 February 2020 Enclosure 5 - WCAP-18455-NP, Revision 1, D.C. Cook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, Westinghouse Electric Company, February 2020. (Non-Proprietary) ML18334A2712018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break. ML18274A0952018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary) AEP-NRC-2018-36, Notification of Initial Renewable Operating Permit2018-05-0909 May 2018 Notification of Initial Renewable Operating Permit AEP-NRC-2018-21, 30-Day Report of Changes to or Errors in an Evaluation Model2018-05-0404 May 2018 30-Day Report of Changes to or Errors in an Evaluation Model ML18026A8822018-02-0505 February 2018 Staff Assessment of Flooding Focused Evaluation ML18334A2692018-01-31031 January 2018 WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2682018-01-31031 January 2018 WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary) ML18334A2702018-01-31031 January 2018 WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology. ML17151A9672017-06-14014 June 2017 Flood Hazard Mitigation Strategies Assessment ML16313A1172016-10-10010 October 2016 1BTl1V001-RPT-01, Donald C. Cook Focused Scope Peer Review - Pre-Initiator Human Reliability Analysis. ML16127A3352016-05-0606 May 2016 Reactor Oversight Process Task Force FAQ Log-April 13, 2016 ML16113A1982016-04-20020 April 2016 Precursor Screening Analysis- Reject ML16169A1182016-03-31031 March 2016 RWA-1313-015, Rev. 1, AST Radiological Analysis Technical Report. 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-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-10-0101 October 2015 Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15233A0242015-08-19019 August 2015 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML14253A3172014-09-0404 September 2014 Enclosure 2: I&M CAP Document AR 2010-1804-10, Root Cause Evaluation Attachment, Rx Vessel Core Support Lug Bolting Anomalies ML14147A3292014-06-18018 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14181A5382014-06-0505 June 2014 Enclosure 5 to AEP-NRC-2014-42, Attachment #2 (NP-Attachment) of Westinghouse Letter, LTR-PL-14-22, Westinghouse Responses to NRC, Request for Additional Information on the Application for Amendment to Restore.. ML14073A7592014-03-31031 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14092A3302014-03-17017 March 2014 Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25 AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model2014-02-27027 February 2014 30 Day Report of Changes to or Errors in an Evaluation Model ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) AEP-NRC-2014-08, SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-4042014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-404 ML14035A3642014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-1 Through Page D-91 ML14035A3682014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-241 Through Page D-321 ML14035A3672014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-170 Through Page D-240 ML14035A3662014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-92 Through Page D-169 ML14035A3522014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Cover Through Page B-312 ML14035A3532014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-1 Through Page C-114 ML14035A3552014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-405 Through End ML14035A3562014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-115 Through Page C-231 ML14035A3572014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-232 Through Page C-353 2024-07-25
[Table view] Category:Technical
MONTHYEARAEP-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 ML22340A2132022-11-30030 November 2022 R1900-0024-001, Revision 13, NFPA 805 Nuclear Safety Capability Assessment ML22340A1992022-11-30030 November 2022 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2) ML22340A1762022-11-30030 November 2022 Commitment Change Summary October 2020 to May 2022 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level2021-01-28028 January 2021 Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level AEP-NRC-2020-23, Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2020-04-30030 April 2020 Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML20108E9992020-03-0505 March 2020 Enclosure 7 - LTR-SCS-19-50, Revision 0, D.C. Cook Unit 1 Low Temperature Overpressure Protection System (Ltops) Analysis for 48 EFPY, Dated March 5, 2020, Attachment 2 Only (Non-Proprietary) ML20108F0002020-02-28028 February 2020 Enclosure 5 - WCAP-18455-NP, Revision 1, D.C. Cook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, Westinghouse Electric Company, February 2020. (Non-Proprietary) ML18334A2712018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break. ML18274A0952018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary) ML18334A2692018-01-31031 January 2018 WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2682018-01-31031 January 2018 WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary) ML18334A2702018-01-31031 January 2018 WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology. ML16313A1172016-10-10010 October 2016 1BTl1V001-RPT-01, Donald C. Cook Focused Scope Peer Review - Pre-Initiator Human Reliability Analysis. ML16169A1182016-03-31031 March 2016 RWA-1313-015, Rev. 1, AST Radiological Analysis Technical Report. 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. ML14253A3172014-09-0404 September 2014 Enclosure 2: I&M CAP Document AR 2010-1804-10, Root Cause Evaluation Attachment, Rx Vessel Core Support Lug Bolting Anomalies ML14147A3292014-06-18018 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14092A3302014-03-17017 March 2014 Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25 ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14035A3642014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-1 Through Page D-91 AEP-NRC-2014-08, SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-4042014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-404 ML14035A3682014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-241 Through Page D-321 ML14035A3672014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-170 Through Page D-240 ML14035A3522014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Cover Through Page B-312 ML14035A3532014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-1 Through Page C-114 ML14035A3662014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-92 Through Page D-169 ML14035A3632014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-845 Through Page C-962 ML14035A3622014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-723 Through Page C-844 ML14035A3612014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-584 Through Page C-722 ML14035A3552014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-405 Through End ML14035A3602014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-469 Through Page C-583 ML14035A3592014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-354 Through Page C-468 ML14035A3572014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-232 Through Page C-353 ML14035A3562014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-115 Through Page C-231 ML13357A3252014-01-10010 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Donald C. Cook Nuclear Plant, Units 1 and 2, TAC Nos.: MF0766 and MF0767 ML14253A3182013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 1 of 3 AEP-NRC-2014-59, Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 3 of 32013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 3 of 3 ML14253A3192013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 2 of 3 ML13267A3272013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-1 Through Page D-48 AEP-NRC-2013-07, SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-405 Through End2013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-405 Through End ML13267A3352013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-339 Through Page D-404 ML13267A3342013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-271 Through Page D-338 ML13267A3322013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-221 Through Page D-270 ML13267A3292013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-115 Through Page D-160 ML13267A3282013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-49 Through Page D-114 ML13267A3252013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-801 Through Page C-884 ML13267A3162013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-312 ML13267A3172013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-98 2022-12-15
[Table view] |
Text
'
~ /
NBC D;RIBUTION FOB PART 50 DOCKE'TEBI (TEMPORARY FOI1M)
/I ~
1' CONTBO'L NO:
/ ,FILE ENVIRO.
s Great a es esearc 1v.
F ROM, 'nn Arbor,'ich.. DATE OF DOC DATE R EC'D LTR TWX RPT OTHER, .
John G. 'Ayers -. 12-15-75 12-22-75 xxx TO: ORIG XXX CC OTHER SENTMC PDR Mr. Charles Domeck 1 Signed SENT LOCAL PDR Cl ASS UNC LASS PROP INFO 'NPUT NO CYS REC'D DOCKET NO'.
315 XXX II, 5Q DESCRIPTION: ENCLOSUR ES:
l Ltr. trans the/ following... Report entitled "Study of the. Horizpntal & Ve Vertical Dist'ribution of. Entranin'ed 'Animals in the, Cook Plant.Intake Forebay.....
i ( 1 cy. Encl..rec.'d) 2 This mail control, replaces m/c .1'4159 4d. 9/h DO:NOT. R PLANT NAME: ACKNOWLEDGED Univ. of Mich.
FOR ACTION/I BUTLER (L) SCHWENCER (L) ZIEMANN (L) RFGAN (E) REID(L)
W/ Copies LV/ Copies VI/ Copies W/ 'Copies W/ COPIES CLARK (L} Sl OLZ (L) DICKER (E) Ll-An (L)
W/ Copies f'Afric (Li W/ Copies ~/
VASSALLO {Li f/Kii!GHTOiv'E)
Copies W/ Copies SPIES
/ Copies W/ Copies V(l/g.opies ~ Vi(l Copies
<iUI EL (L) PURPLE (L) YOl7NGBLOOD (E) LPif
)V/l Copies W/ Copies W/ Copies W/" opies INl E R MAL D I STB I BU TION
's TEGH REvIEw DEN1ON L IC ASST A/T INI) .
DB SCI< ROE DE R GB IMiES R; DIGGS {L) B RA ITiYiAN C, BOOM P-50BA MACCARY GAMMILL H. GEARIN (L) SALTZMAN OSSI CK/STAF F I>NIG HT KASTNER E GOUI BOURNE (L) ME I TZ CASE ~A V)l LIC K I BALLARD P. KRFUTZER {E)
Sf.IAO SPANGLER J. LEE (L) . rLANS BOYD STELLO M. RU3iiMOOK(L) MiCDONAI D
~CIORE (L) HOUSTON 5 REED (E) CHAPMAN DEYQUNG (I }
SKOVHOLT (L)
NOVAK MULLLR v9. SEfiVICE (L) DUBE (Ltr),
ROSS DICKER S, SI-I.L.PPARD (I } E. COUPE GOI LER (L) (Ltr)
P. COLLINS IPPOLITO TEDESCO l<NIGHTON YOUNGBLOOD
~. SLA I ER (E)
H. SfAI I H (L)
PETERSON HARTI=IELD {2)
@GO" .(a FILE St REGION(EE J,COLT.IHS LAINAS BENABOYA GAN ROJECT LDR C IP S. TEETS (0 G, WII LIAMS (E)
V. WILSON (L)
~
I<LEG!iER
'ISENHU.r Wl GG INTON MD'C VOI LMER ti t) R'..E SS B. INGBs<<{L)
II. PU)~SCAN Q K. I'ARRISH"" L EX r . nNAL DISTR I BU1'ION w-W- LOCAL PDR.
rlc {ABI-RK!ATHY (1)(2) 'IO} NATIONALLABS P D R-SAN/LA/NY H-NSIC {BUCHANAN) 1 W. PENNINGTON, Rim L.-201 GT 1
1 BRQOI<l-IAVEN NAT I AB 1 ASLB 1 CONSULTANTS 1 G. ULRIKSON ORNL 1 Newton Anderson .NEWiMAI<K/BLUi),'!E/AGBABIAN CRS I 9+)&!)LAPSE 7ts ~Pf vi QG, 51 5'
cl
'k g
~ i>
't(
I
' "a
GULATORYy)OCKETFILE CQ."",.
ssar zsss Rsssasc zvrsrox THE UNIVERSITY OF MICHIGAN II ~q INSTITUTE OF SCIENCE AND TECHNOLOGY BUILDING ANN ARBOR, MICHIGAN48105 313/264.2420 Ot
)
December ',15,,1975
'Mr. Charles Domeck PL P oject M nager b Directorate of Licensing Nuclear Regulatory Commission Washington, DC 20545
Dear Mr. Domeck:
Attached is an informal report, "Study of the horizontal and vertical distribution of entrained animals in the Cook Plant intake forebay", by Samuel C. Mozley and Edward M. Johnston. We are sending it to keep you informed on our search for an optimum sampling location within the forebay.
The Technical Specifications:(p. 4 .1-27) have required us to look at possible stratification within the forebay before deciding on a permanent sampling location. The studies are now complete, and we have decided to ask the Company to install two permanent sampling pipes at screen MTR 1>>5, just upstream of the trash bars. (This location is shown in Figure 1 of the attached report:). Both pipes will draw water from a depth of 5.6 meters below the surface; two pipes are needed so that zooplankton and fish larvae samples can be collected simultaneously during the same 24>>hour period.
Other procedures will continue unchanged.
The chosen location is near the center of what we believe to be the main path of water flow into Unit I. The depth is close to the mean depth of the forebay. Before making this choice, we compared the results of sampling from a number of different locations within the forebay. Details are given in the attached report.
So far as we know, installation of these fixed pipes is. permitted by the Tech. Specs and does not require any government'pprovals. We are writing keep you to informed on our progress and to provide an opportunity for any comments you may wish to make. If any further information is desired, please contact us. A copy of our letter to the Company requesting the pipes is enclosed.
Our records do not contain your current title and mailing address at the NRC. We would appreciate learning the correct version if different from the one used above.
Sincerely, hn C. Ayers Research Oceanographer Enc: (1) Report (2) Copy of letter to AEP
4 C
~ w
$ F g
'll I
A stud of the horizontal and vertical distribution of entrained animals in the Cook Plant intake foreba (This report was compiled from available project data on 12-11-75, by Samuel C. Mozley and Edward M. Johnston)
The relevant section of the Environmental Technical Specifications is 4.1.2.1.3, on page 4.1<<27: "Study of Plankton, Benthos and Fish Egg and Larvae Intake Entrainment. " We quote below the two passages that concern the choice of a sampling location:
Fish Entrainment and Entrainable Benthos (p. 4.1-27)
'Tish, fish larvae, fish eggs, and benthos shall be sampled at two locations: in the intake forebay and discharge forebay following passage through the condensers. Testing shall be done during 1974, to determine existence or non-existence of vertical strati-fication in the intake and discharge forebays; three depths shall be sampled: near the bottom, at mid-depth and near the surface.
If vertical stratification is, or is not, observed, sufficient samples to meet statistical reliability shall be taken in each forebay. "
Zoo lankton Entrainment (p. 4.1-28)
"Zooplankton samples shall be collected in the intake forebay,
..discharge forebay following passage through the condenser, and within the plume... .After preliminary experiments to determine whether horizontal or vertical stratification exists and to choose a representative sampling position, statistically reliable (e.g., replicate samples) sampling shall be performed at least monthly. "
After making the studies required above, we have selected screen MTR 1>>5 (Fig. 1) as the location for a permanent sampling pipe, which will draw water from 5.6 meters (18') below the intake forebay water surface. There is always the chance that the results would be different if samples were drawn from a different location, but the studies have con>>
vinced us that such differences would be negligible. The chosen location is
~ ~
I J ~
'i
INTAKES (DEPTH=9m)
SOUTH Om NORTH DISCHARGE DISCHARGE (DEPTH=6m) (DEPTH-Gm) 370m 370m LAKE MICHIGAN SHORE INTAKE SAMPLING LOCATIONS INTAI(E FOREBAY
)
cv M cv & w cv I UNIT 1 TRASH BARS DISCHARGE FOREBAY TRAVELING SCREENS DISCHARGE SAMPLING I
LOCATION (X)
CIRCULATING I VOTER PUMPS J
CONDENSER UNIT 2 CONDENSER UNIT Figure 1. Diagram of the intake and discharge forebays of the Cook Plant, showing the numbering system for the travelling screens. Xt is proposed to install two permanent sampling pipes in front of screen EZR 1-5.
near the center of what we believe to be the main path of water flow into Unit X. The depth is close to the mean depth of the forebay.
If the horizontal and vertical distributions of plants and animals within the forebay were very uneven, it is possible that a .permanent" bias in our abundance results would result. This might occur if the single sampling point had consistently high or consistently low abun-dance, month after month, compared to the true mean of the forebay.
It is possible to check for the presence of bias at our chosen location by taking samples at the chosen location and at a number of alternative locations. The best available estimate of the true forebay mean abun-dance of a taxon at a given moment is the mean of the values found at all locations sampled. The mean at oux chosen location can then be compaxed to the mean of all locations; to determine the extent of any bias. Repeated samples at each individual location will give varying because of time variations and the normal sampling-associated 'esults errors. No bias should be considered serious if it is similar in magni-tude to the variation that noxmally occurs between replicates. The error due to variation among replicates can be used to set 95% confi-dence limits on the bias estimate at the chosen sampling location. The scheme that we use to find the limits is a straightfoxward one-way analysis of variance. The bias at our chosen location is simply the main effect (L ) at that location. The linear model for the ANOVA is as follows:
Y..
sJ
=y+L.i + c..
.
is the iJ'here:
YES abundance of the given taxon at location s, as measured by the Jth replicate p is the true grand mean of all locations LE is the true difference between the mean at the ith location and the mean of all locations s ~ ~ is the error in the Jth replicate at the ith location The index s runs over all locations sampled and J runs over replicates at I each location Por each taxon, the measured abundances are analyzed with the above model to obtain an estimate of L and to set 95% confidence limits on the estimate. The .statistic used to estimate L is the difference between the mean of the replicates at the chosen location and the mean of all replicates at all locations. The 95% confidence interval can be found using a formula given by Kirk~, that applies to any contrast. Xn our case, Kirk's expression gives the following confidence limits:
(p-1) "
Pr MSe MS (p-1) c . 05[@]
Ppl c c .05[v] pn P
where: Lc is the difference between the mean of replicates at the chosen location ('c') and the mean at all locations MSe is the within-cell error mean square of the analysis of variance p is the number of locations sampled m is the number of replicates at each location Kirk, Roger E. (1968): Ex erimental Desi n: Procedures for the Behavioral Sciences, (Brooks/Cole, Belmont, Calif.) P, 74
5 is the number of degrees of freedom of the error mean square.
This analysis was carried out separately for each group of organisms.
Sam lin Methods Methods for drawing samples from the forebay were basically the same for all groups. Diaphrayn pumps with a rated capacity of 360 liters per minute pumped water through flexible plastic hoses which were lowered to the desired sampling depth through grates above the forebay. Zooplankton 3
were strained from approximately 0.5 m of water, as measured by flowmeters or time of pumping, and concentrated in N'10 mesh Nitex nets. Suspended benthos were strained from about 2.5 m of water collected by pumping for 10 minutes and concentrated on N2 mesh Mitex nets. To collect fish larvae the pump."was run for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time, drawing a sample of about 50 m .
Several locations spread across the forebay were selected, each being sampled at one to three depths depending on the design. The selected locations were sampled for the appropriate volume either simultaneously by use of up to three sampling pumps or sequentially with a single pump by moving the hose. Sequential sampling was assumed to give adequate replication in all cases. Replication 6f fish larva observations was obtained by taking corresponding four-hour periods on successive days as replicates.
The Dischar e Poreba The Technical Specifications, in the first of the two paragraphs quoted on page 1, mention a study of vertical stratification in the discharge forebay. Xt appears that the suggestion for this requirement was originally made by us. At that time the discharge forebay was still accessible for hose sampling. Since then it has been covered by a
l
~ ~
1
~ ~
6 metal deck, apparently to help control surges in the circulating water syst: em. Sampling now occurs through a rigid pipe, and it is not possible to sample at more than one depth. We will necessarily remain ignorant of the variation (if any) of abundances with depth in the discharge bay.
However, the water velocity there is considerably /
higher than in the intake forebay. Xt is reasonable to assume that it is better mixed.
Results -- Zoo lankton Seventy-two samples were taken in the intake forebay on August 6, 1974.
Analysis of variance with the following layout was performed on total animals per m : grates (3) x depths (3) x times (2) x day/night (2) x replicates (2). A pair of replicates consisted of two successive two-minute samples. The';error degrees of freedom are found to be 3 x 3 x 2 x 2 x (2-1) = 36. The grates sampled were 11TR 1-1, 1-3 and 1-5 (Pig. 1);
depths were 2', 18'nd 28'. The location we propose for the permanent pipe (HTR 1>>5, 18') was among those sampled. Xts bias was +24.6% of the mean of all samples; the 95% confidence limits for the true bias were
+ 30.8% of the mean.
Results -- Benthos Benthic animals may be stirred up off the bottom, and some may swim into overlying water actively, where they are exposed to entrainment into the Cook Plant. Samples collected for fish larva studies in the intake forebay are also examined for benthic macroinvertebrates and; u their density in the forebay is estimated. A comparison of their den"ities at different locations was made on August 6 and 7, 1974, using 10-minute samples.
in entrainment studies, these were too rare in summer samples to support in density in the forebay would act similarly on Chironomus larvae which are about the same size. The higher abundance of Chironomus makes spatial comparisons possible with some degree of confidence. The benthos were more abundant at night in this study. The mean of 18 night samples was 7.37 animals per m ; the mean of the 18 day samples was 1.11 per m .
The analysis below was done on the night data. Figures for total animals exclude ~Hdrawh,ich we assume is growing on the inside of the intake pipe.
The bias at 18'or location MTR 1-5 was +79+77% for total animals and -16+ 79% for Chironomus. Of the two, the estimate for Chironomus is The confidence limits (77% and 79%) may appear wide. Pumping for a longer period than 10 minutes would presumably have led to narrower confidence limits. But before diverting greater effort into sampling benthos, w'e should note'hat the'otal weight of entr'ained benthos is very small compared to that of zooplankton. Our estimate of the wet weight of zooplankton entrained by the Plant every year is 4,670,000 kg.,
while the weight of benthos entrained is estimated as 7,060 kg.
Results Fish Larvae Depth variations were examined in one 48-hour study, and grate variations in a second 48-hour study in the period from July 29 to August 2, 1975. Those dates were selected because fish larvae densities near the Cook Plant were expected to be near their annual maximum.
In the depth study all observations were made at grate HTR 1-4; the density of larvae at 18'as compared to the mean density at all three depths (5', 18'nd 28'). The bias at 18'as found to be -}47.4+ 39.6%.
t 0 P
In the grate study all observations were made at 18 '; the density of larvae at MTR 1-4 was compared to the mean density at three different grates (MTR 1-4, 2-2 and 2-6). The bias at MTR 1>>4 was found to be +53+ 67%.
Pish samples were not taken at the location we are now recommending for the permanent pipe (MTR 1-5, 18'). We trust that the difference between MTR 1-4 and MTR 1-5 is not important.
Note that the bias values produced by both the depth and grate studies for fish larvae are positive, and thus on the conservative side. If consis-.':
tently present they would lead to an overestimate of the abundance of larvae, and thus an overestimate of the environmental damage due to the plant,.
The reader will notice that most of the bias figures %or benthos and zooplankton were also positive, and thus on the safe side," although only marginally significant in most cases.
Conclusion A permanent sampling pipe at MTR 1-5, drawing water from a depth of 18 ', will give a reasonable estimate of the density of animals in the water entrained by Unit I.
\
~ '
A
'azer Lniczs Rsazca Dzvzssox TIIE UNIYERSITY OF ~IICIIIGAN INSTITUTE OF SCIENCE AND TECIINOLOGY DUII.DING ANN ARDOR, ~iIICHIGAN4SIOS 313/764.2420 C OPY December 4, 1975 Mr. J. LeMasters Cook Nuclear Plant Bridgman, Michigan 49106
Dear Sir:
This letter concerns a request that Indiana and Michigan Power Company assist our environmental studies at the Cook Plant by installing pipes in the intake forebay of the plant. The pipes will be used to fixed'etal pump samples of water from which we can estimate the number and condition of suspended plants and animals before they pass through the condensers.
At present,.we are using flexible plastic hoses which can be lowered at any desired 'location to any depth. These were necessary in the early phase of our entrainment studies to permit estimation of the amount of variation which occurs in the densities of organisms from place to place in the fore-bay. That task has been completed, and we have now selected a permanent sampling location for Unit 1 entrainment studies.
A separate letter is being sent to Charles Domeck of the Nuclear Regulatory Commission. We are not certain whether his approval of our sampling design is necessary, but felt it a good idea to inform him before we proceeded to a permanent sampling installation. The Technical Specifica-tionsl require that a "representative sampling location" be chosen, and that the existence of horizontal or vertical stratification be determined. Since we believe we have met the spirit and the letter of the specification, we do not anticipate that he will object to our selection.
The permanent sampling location in the forebay will be (as it has been for more than a year) just upstream of the trash bars in front of traveling screen motor MTR 1-5. The intake of the sampling pipe will be at a depth of 18 feet below the water level in the forebay. The best way to establish the forebay water level on the average is not clear from information avail-able to us. We have been measuring the depth directly each time we sample If the intake forebay water level is related to the "Lake Michigan datum" for mean water level by some constant difference, we suggest that the samp-ling intake be located 18 feet below the "Intake datum-equivalent" for mean water level in Lake Mich'igan. Preferably, the sampling intake should not be closer than several feet to massive structures of the forebay.
P. 4;1-28, "Zooplankton Entrainment," paragraphs 1 and 2, for example.
Mr. J. LeMasters December 4, 1975 Page 2 Engineers familiar with the forces operating in the forebay and the technical requirements of safe function of the circulating cooling water system are better able than we to design a specific installation. How-ever, we would like to specify that two pipes be installed side-by-side, each with three-inch internal diameter and suitable at the upper end for connection with our present sampling pumps (we use O.P.W. Kamlok fittings, I/'s 633E and 633C). There should also be check valves at the upper ends of the pipes, accessible to rapid service in case of malfunction or clog-ging. The tops of the pipes should be spaced far enough apart (8") to permit u'se of a pipe-wrench on the check valves. We neet two pipes in order to be able to attach two of our sampling pumps and double the vol-ume which can be sampled from that point over a given time interval.
We realize that considerable time and expense may be incurred in the design and installation of the pipes, but we cannot maintain a program without some improvements in the present system. Our suitable'ampling flexible hoses are wearing out, fraying and leaking. The check valves at the intakes of present hoses require frequent service.'e have found it necessary to send additional employees to the plant site in advance of every entrainment sampling period to install and check the hoses and repair them when necessary. The necessity of working near open ports in the cover of the forebay has always concerned us, particularly because of the heavy work, hauling and lowering hoses and grates which cover the ports, which we must do near the open ports. We are convinced that a durable, safe and consistent sampling installation is essential to continued effectiveness of our entrainment monitoring program. Needless to say, we would appreciate rapid action on our request.
Sincerely, Samuel C. Mozley Asst. Research Limnologist John C. Ayers Project Director cc: Druckemiller Domeck
V 4
P