|
---|
Category:Drawing
MONTHYEARML23135A1282023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 18, Figures ML23135A1192023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 8, Figures ML23135A1182023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 6, Figures ML23135A1672023-05-0808 May 2023 6 to Updated Safety Analysis Report, Figures ML23135A1232023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 11, Figures ML23135A1242023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 5, Figures ML23135A1272023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 12, Figures, Redacted ML23135A1212023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 7, Figures ML23135A1202023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 9, Figures, Redacted ML23135A1262023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 1, Figures - Redacted ML23135A1252023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 2, Figures ML23135A1222023-05-0808 May 2023 6 to Updated Safety Analysis Report, Chapter 10, Figures ML23045A1952023-02-14014 February 2023 Transmittal of the National Pollution Discharge Elimination System Permit Renewal Application for Wolf Creek Generating Station I-NE07-PO02 ML22152A1692022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 8, Figures ML22152A1832022-05-18018 May 2022 M-6630-00017A, Appendix G3D to Attachment H, Structural Steel Fireproofing Data, Page G3D-1 of G3D-50 to G5A-63 of G5A-63 ML22152A1772022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 12, Figures - Redacted ML22152A1742022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 5, Figures ML22152A1722022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 10, Figures ML22152A1762022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 1, Figures - Redacted ML22152A1732022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 11, Figures ML22152A1682022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 6, Figures ML22152A1702022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 9, Figures ML22152A1712022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 7, Figures ML22152A1752022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 2, Figures ML22152A1782022-05-18018 May 2022 5 to Updated Safety Analysis Report, Chapter 18, Figures ML21168A1252021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 8, Drawing No. KD-7750, Revision 14, Wolf Creek Substation General Plan ML21168A1262021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 9, Drawing M-12EC01, Revision 23, Piping & Instrumentation Diagram Fuel Pool Cooling and Clean-Up System. Redacted ML21168A1112021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 2, Figures ML21168A1282021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 10, Drawing M-12AC01, Revision 30, Piping & Instrumentation Diagram Main Turbine ML21168A1292021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 11, Drawing M-12HB01, Revision 16, Piping and Instrumentation Diagram Liquid Radwaste System ML21168A1342021-06-0707 June 2021 4 to Updated Safety Analysis Report, Chapter 18, Drawing M-12SJ04, Revision 16, Piping and Instrumentation Diagram Nuclear Sampling System ML20290A6012020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 18, Drawing M12SJ04, Sheet 16, Piping and Instrumentation Diagram ML20290A5992020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 11, Figures ML20290A5982020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 10, Figures ML20290A5912020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 2, Figures ML20290A5972020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 9, Figures ML20290A5962020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 8, Figures ML20290A5922020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 5, Figures ML20290A5692020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Figures ML20290A5942020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 7, Figures ML19092A0682019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 7, Figure 7.2-1-01 Thru 7.2-1-18 & 7.6-4-2 ML19092A0822019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 18, Figure 18.2-15-00 ML19092A0762019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 11, Figures 11.2-1-01 - 11.4-1-04 ML19092A0722019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 9, Figure 9.1-3-01 Thru 9.5.10-03, Redacted ML19092A0602019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 1, Figure 1.1-1-02 Thru 1.2-44, Redacted ML19092A0622019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 2, Figure 2.4-3-2 Thru 2.4-3-07 ML19092A0642019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 5, Figure 5.1-1-01 Thru 5.4-21 ML19092A0662019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 6, Figure 6.2.2-1-00 Thru 6.3-1-04 ML19092A0702019-03-11011 March 2019 Revision 32 to Updated Safety Analysis Report, Chapter 8, Figure 8.2-3 Thru 8.3-7-00 ML18093A9452018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Chapter 1, Drawings. Redacted 2023-05-08
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T WM 14-0013, Voluntary Commitment Regarding Containment Coolers at Wolf Creek Generating Station2014-05-0808 May 2014 Voluntary Commitment Regarding Containment Coolers at Wolf Creek Generating Station WO 14-0032, Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-03-26026 March 2014 Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ET 14-0011, Second Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-02-26026 February 2014 Second Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events WM 13-0014, Commitment to NRC Regarding Actions Necessary to Increase Safety Margins Through Ongoing Actions to Resolve Substantive Cross-Cutting Issues (Sccis)2013-06-27027 June 2013 Commitment to NRC Regarding Actions Necessary to Increase Safety Margins Through Ongoing Actions to Resolve Substantive Cross-Cutting Issues (Sccis) ML1019004182010-06-28028 June 2010 Quick View Chart ML1016806592010-06-16016 June 2010 6/16/10 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Baseline Risk Values for Wolf Creek ET 09-0031, Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-022009-11-0404 November 2009 Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02 ET 09-0026, Notification of Deviation from EPRI Pressurized Water Reactor Secondary Water Chemistry Guidelines2009-10-25025 October 2009 Notification of Deviation from EPRI Pressurized Water Reactor Secondary Water Chemistry Guidelines ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0426101132004-09-13013 September 2004 Plant Engineering Branch Open Items Interim Safety Basis (URI 2002003-01) 2023-05-17
[Table view] Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Photograph
MONTHYEARML16076A2992016-03-0303 March 2016 Wolf Greek Generating Station - After Action Report/Improvement Plan ML13246A3622013-08-29029 August 2013 Photographs of Pictures of Cables from Wolf Creek ML13058A2072013-02-26026 February 2013 Ongoing SG Inspection Results for RFO 19 ET 09-0031, Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-022009-11-0404 November 2009 Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02 ML0714303632007-05-0909 May 2007 Responses 2 - 10, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714303562007-05-0909 May 2007 Response 1, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application, Consisting of Aerial Photographs of the Site Dating Back to Before and During Site Preparation and Plant Construction ML0714303532007-05-0909 May 2007 Response 1, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application, Consisting of 1991 Coffey County Post Construction Image ML0714303522007-05-0909 May 2007 Response 1, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application, Consisting of 1979 Coffey County Preconstruction Image ML0714303502007-05-0909 May 2007 Response 1, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application, Consisting of 1985 Neosho River Between Burlington and Leroy Ks ML0714303472007-05-0909 May 2007 Response 1, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application, Consisting of 1985 John Redmond Reservoir 2016-03-03
[Table view] |
Text
WF CREEK NUCLEAR OPERATING CORPORATION Terry J. Garrett Vice President Engineering November 4, 2009 ET 09-0031 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
Subject:
- 1. Letter ET 08-0003, dated February 29, 2008, from T. J. Garrett, WCNOC, to USNRC 2. Letter ET 08-0053, dated December 22, 2008, from T. J.Garrett, WCNOC, to USNRC 3. Letter dated July 31, 2009, from USNRC to R. A. Muench, WCNOC (ADAMS Accession No. ML092030628)
- 4. Letter dated September 28, 2009, from USNRC to R. A.Muench, WCNOC (ADAMS Accession No. ML092460714)
Docket No. 50-482: Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors" Gentlemen:
By letter dated July 31, 2009 (Reference 3), NRC transmitted a request for additional information (RAI) regarding the Wolf Creek Nuclear Operating Corporation (WCNOC)responses to Generic Letter (GL) 2004-02 (References 1 and 2, ADAMS Accession Nos.ML080700356 and ML090060877, respectively).
WCNOC and Union Electric Company (AmerenUE) subsequently participated in a public phone call with the NRC on August 27, 2009 (Reference 4). During the August 27th phone call with the NRC, WCNOC and AmerenUE agreed to provide a video of the testing performed by ALDEN Research Laboratory, Inc. (Alden)showing separation of the fibrous debris in representative and conservative manner for NRC staff review.Pursuant to 10 CFR 50.54(f), this letter provides video descriptions of the Alden testing in support of WCNOC's response to the NRC's GL 2004-02 RAIs (Reference 3). Enclosure I to this letter provides a description of the transport tests performed, and Enclosures II and III provide the digital video disks (DVDs) of two transport tests. As stated in Enclosure I, the vendor testing performed supports both Wolf Creek Generating Station and Callaway Plant.P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET 41ý)kl4lý-
ET 09-0031 Page 2 of 3 No regulatory commitments are made to the NRC by this letter. If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr. Richard D. Flannigan at (620) 364-4117.Sincerely, Terry J. Garrett TJG/rlt
Enclosures:
II IIl Alden Video Description of the Fiber Debris Transport Testing Video of Flume Transport Test #1, Latent Fiber Transport Test Video of Flume Transport Test #2, Smalls Transport Test cc: E. E. Collins (NRC), w/e G. B. Miller (NRC), w/e B. K. Singal (NRC), wle M. C. Thadani, (NRC), wie Senior Resident Inspector (NRC), wo/e ET 09-0031 Page 3 of 3 STATE OF KANSAS )SS COUNTY OF COFFEY )Terry J. Garrett, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.TerBJ. Garrett Vice President Engineering SUBSCRIBED and sworn to before me this LV/, day of oovember-2009.RHONDA L. TIEMEYER Notary Public v--SA.- My COMMISSION EXPIRES J......anuary 11, 2010 Expiration Datej01aUZ2JJ
/ )#T Enclosure I to ET 09-0031 Page 1 of 11 Enclosed is the report by ALDEN Research Laboratory, Inc. describing the fiber debris transport testing performed for Wolf Creek Generating Station and Callaway Plant.
A LDEN -olving TIOW problems since November 2, 2009 Fiber debris transport testing for the Wolf Creek and Callaway power plants For the testing there are two video cameras that are taping the flume. The right most screen is the upstream camera and is intended to show the debris introduction.
The left camera shows the transport of material downstream of the introduction.
Flow is therefore from right to left for both video screens.The testing was conducted in the small flume for visualization purposes.
The testing is intended to replicate flume velocities generated during full scale head loss testing completed previously for the Wolf Creek and Callaway power plants. The velocity plot used for full scale head loss testing is shown in Figure 1, and the wall geometry tested in full scale head-loss testing is shown in Figure 2.1 bV4 0.33 0.31 0.29 SO0.27.2 0.25 0.23 0.21 0.19 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 Distance Back From Sump Edge (FT)Figure 1. Approach velocity profile ALDEN Research Laboratory, Inc.30 Shrewsbury Street, Holden, Massachusetts 01520-1843 508-829-6000/phone
- 508-829-5939/fax info@aldenlab.com
- www.aldenlab.com ALDEN-2-November 2, 2009 Lengthwise Dimensions Widthwise Dimensions o Figure 2. Large flume configuration For the small flume tests documented herein, the approach velocity profile over the last 16 feet of flow stream is replicated, corresponding to the region of the profile containing the slowest velocities.
Replicating the slowest velocities represents a conservative approach to showing that the latent fiber settled on the floor after introduction with the pump stopped can be readily transported to the strainers.
Likewise, replicating the slowest velocities for debris introduction is conservative because the shear induced release of fines will be relatively lower at lower velocities.
The flow rate to achieve the target velocities is approximately 439.4 gpm. The flume plan view is shown below in Figure 3. The flume water depth for the present testing is maintained at the large flume test level of 28".Figure 3. Small flume flow configuration ALDEN-3-November 2, 2009 rigure 4. Clean strainer at start ot test Test 1 Nukon fines added to a quiescent flume water column 0 0:00 -0:51 (14:32:59
-14:33:50):
The pump for the flume is off and the flume is quiescent. (Figure 4)* 0:51 -2:25 (14:33:50
-14:35:24):
The Nukon fines (0.25 ibm), prepared as during head loss testing with electric drill and mixing paddle, are being added across the length of the flume. The fiber breaks up upon entry into the flume. The fiber falls relatively uniformly, while some clouds of less dense fiber can be observed.
ALDEN-4-November 2, 2009 Figure 5. Latent fiber settling on flume floor* 2:25 -8:43 (14:35:24
-14:41:42):
The fiber has all been placed into the flume, and the five minute settling period has begun. All of the fiber will have settled onto the flume floor by the end of this five minute period.0 8:43 -10:05 (14:41:42-14:42:04):
The pump has just been started and the flow rate of 439.4 gpm or slightly higher has been established in the flume. The fiber can be observed moving downstream.
A cloud of fiber is lifted off of the flume floor and transports downstream.
Figure 6. Latent fiber leading edge being pulled downstream ALDEN-5 -November 2, 2009* 10:05 -16:40 (14:42:04
-14:49:39):
More than half the fiber has moved downstream and little fiber remains to be transported.
The movement of the fiber downstream is still occurring but at a reduced rate (Figure 6).* 16:40 -37:18 (14:49:39
-15:10:17):
More than 3/4 of the fiber has transported to the strainer by this time. The last small tufts of fiber are bein trans orted to the strainer.Figure 7. Latent fiber on screen at test termination The quantity of Nukon fines introduced represents the smallest quantity that allows straightforward visualization of transport.
Based on the surface area of the flume model, the directly scaled debris quantity would have been 0.125 Ibm. It is conservative to determine fiber transport with a higher density of fiber settled on the floor as the likelihood of generating larger agglomerations that do not transport to the strainer is greater.Figure 8 shows the head loss profile as a function of time at the strainer.
Although absolute measured values do not have particular meaning, the profile of head-loss is still relevant.
On this time scale (not synchronized to the video), the pump is started just beyond the 6 minute mark. The head loss rises quickly due to the transported fiber. The rate of increase slows considerably with time, as expected.
The head-loss curve also confirms that a large portion of the introduced latent fiber, greater than 80%, was transported to the strainer within 15 minutes of pump start. Visual inspection of the flume at the end of testing confirmed that all latent fiber transported to the strainer area. This conclusion is further supported by the very flat head loss curve near the test termination.
ALDEN-6 -November 2, 2009 1.9 1.85 1.8 1.75 1.7 o 1.65 1.6 1.55 1.5 1.45 1.4 00:00 05:00 10:00 15:00 20:00 25:00 30:00 35:00 40:00 45:00 50:00 Test time (min:secs)
Figure 8. Head-loss profile for latent fiber addition ALDEN-7 -November 2, 2009 Test 2 Nukon Smalls added to the flume with an established flow* 0:00 -1:37 (15:34:54
-15:36:31):
The flow rate of approximately 439.4 gpm is established in the flume.* 1:37 -2:51 (15:36:31
-15:37:45):
The Nukon small fiber is added in the same manner as the fiber was added in the large flume testing. A total of 2.24 lbs of Nukon has been introduced into the flume at this time. A debris cloud of lighter fiber can be observed breaking away during the introduction (Figure 9).e 2:51 -5:00 (15:37:45
-15:39:54):
The lighter smaller fiber and individual fiber is transporting to the strainer at this time, while the heavier fiber material is starting to accumulate on the floor (Figure 10). It should be noted that small agglomerations of fiber or "clumps" can be seen entering the water column on introduction.
These small clumps form very quickly in the introduction vessel. The water used to wet and prepare the debris is hot (approximately 120 0 F, similar to the conditions for head loss testing) to remove entrapped air. This also leads to rapid settling of the fiber to the bottom of the introduction vessel (fiber settles very quickly in hot water) once mixing has ceased. The clumps are thus not formed by inadequate mixing but by rapid settling of the fiber in the preparation bucket. As such, the clumps that are formed from fiber loosely settling in the introduction vessel can be seen to break up readily in the water column and release entrapped fines and disintegrate into even smaller clumps of fiber. The video shows what appear to be several additions of fiber. However, the additions represent the rinsing of the fiber from the bottom of the bucket which is also performed during head loss testing.
ALDEN-8 -November 2, 2009 Figure 10. Fibers settling in flume downstream of introduction 0 5:00 -6:02 (15:39:54
-15:40:56):
The flow rate is still being maintained.
At this point in time a large pile, approximately 6" high and several feet long has established itself in the flume. This pile is located approximately 10 feet from the area of introduction.
The velocity at this point is lower than the introduction zone causing the debris transport to slow. The velocity profile followed for the flume parallels the selected portion of the head loss flume approach velocity profile (see above). The settling observed here is prototypical of large flume head-loss tests at similar velocities.
-15:41:52):
All of the fiber has been added to the flume.* 6:58 -9:51 (15:41:52
-15:44:45):
The fiber that has been introduced into the flume has all either settled or transported to the strainer.
The fiber that is moving in the video is all being transported across the bed of fiber on the flume floor. The fiber pile is releasing small tufts from the leading edge of the debris pile.* 9:51 -50:00 (15:44:45
-16:24:54):
The release of tufts from the leading edge of the fiber pile continuously slows. Some additional small fiber pieces continue to break away, but the pile size and shape remains largely unaffected.
-16:29:59):
Documentation of the location of the fiber has taken place at this time.The introduced quantity of smalls is calculated based on a volume flow rate ratio between the head loss test and the presently conducted transport test. The scaling on flow rate is appropriate for drop-zone introduced debris. The total amount of smalls introduced for the transport test is further divided by the number of batches employed to introduce the debris into the head loss test (5). The transport test thus reproduces appropriately the debris concentration employed during head loss testing.Figure 11 shows a picture of the strainer near the end of testing. It is clear from this picture that a significant amount of fines were released from the smalls and traveled to the strainer.
Given that Figure 7 shows the picture of 0.25 lb of latent fine fiber on the screen, it is possible to ALDEN-9-November 2, 2009 conservatively conclude that at least twice this amount separated from the introduced small fiber and made it to the strainer in the smalls introduction test.Figure 12 shows the head-loss profile as a function of time for this test. Note the relatively quick steep initial increase.
This is evidence of fines directly transported through the water column to the strainer.
The slower rate of increase later in the test is indicative of floor transport of debris and is much more gradual. However, the most significant jump in head loss occurs in the early part of testing and supports the significant fines release estimate made above. The transport time for the flow to move from the introduction zone to the strainer is approximately 2 min 30 secs, based on an average velocity of 0.21 ft/sec over the modeled length of the head loss flume.Based on this and the fact that debris introduction starts at approximately 1 min 37 secs into the test, debris suspended in the water column would begin causing an increase in head loss at approximately 4 minutes as observed in Figure 12. Furthermore, note that debris introduction ends at 6 min 58 secs into the test. Fiber transported suspended through the water column from the last amount of introduced fiber therefore is expected to reach the strainer at 9 min 30 secs.The head loss curve shown in Figure 12 shows a clear change in the slope at this point. It can therefore be concluded that a significant amount of fiber separated upon introduction and traveled to the strainer suspended in the water column, a behavior consistent with fiber fines.Note that the video shows further release of fine fiber tufts that transport to the strainer and cause the slower rate of head loss increase observed over the remaining period.
ALDEN-10 -November 2, 2009 2.8 2.7 2.6 2.5 2.4 A 2.3 2.21 2 1.9 1.8 00:00 05:00 10:00 15:00 20:00 25:00 30:00 35:00 40:00 45:00 50:00 Test time (min:secs)
Figure 12. Head loss profile in time for smalls addition Enclosure II to ET 09-0031 Page 1 of 1 Enclosed is the digital video disk (DVD) submittal of the ALDEN Research Laboratory, Inc. test described in Enclosure I. The DVD is labeled: Flume Transport Test #1, Latent Fiber Transport Test.
Enclosure III to ET 09-0031 Page 1 of 1 Enclosed is the digital video disk (DVD) submittal of the ALDEN Research Laboratory, Inc. test described in Enclosure I. The DVD is labeled: Video of Flume Transport Test #2, Smalls Transport Test.