Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML12092A0002012-03-28028 March 2012 NRR E-mail Capture - FW: ME7277 - Kewaunee - Review of Rvi Inspection Plan RAI Set 1 of 2 (Rev1) Project stage: RAI ML12125A2972012-05-0303 May 2012 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information Project stage: Response to RAI ML12228A7232012-08-20020 August 2012 Proposed Relief Request 11-CN-001 for the Third Ten-Year Inservice Inspection Interval (TAC Nos. ME7277-ME7283) Project stage: Other 2012-05-03
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0021, Refuel 26 (C1 R26) Inservice Inspection (ISI) Report2022-01-26026 January 2022 Refuel 26 (C1 R26) Inservice Inspection (ISI) Report RA-21-0223, Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-08-0202 August 2021 Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0391, Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-12-19019 December 2019 Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0092, Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-03-11011 March 2019 Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-067, ASME OM Code In-Service Testing Program Document2016-08-31031 August 2016 ASME OM Code In-Service Testing Program Document CNS-16-042, Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval2016-06-13013 June 2016 Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval CNS-16-020, Inservice Inspection Report for End of Cycle 22 Refueling Outage2016-03-18018 March 2016 Inservice Inspection Report for End of Cycle 22 Refueling Outage ML15280A3422015-10-0505 October 2015 Fourth Inservice Inspection Interval Steam Generator Tube Plan ML15238A8832015-08-19019 August 2015 Fourth Inservice Inspection Interval Plan and Inservice Inspection Interval Pressure Test Plan CNS-15-074, CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related2015-08-13013 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A9002015-08-12012 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A8982015-08-12012 August 2015 CISI-1462.10.0040-ISI, Revision 1, Fourth Interval Inservice Inspection Plan CNS-15-061, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage2015-07-0606 July 2015 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage ML15238A8962015-06-23023 June 2015 Fourth Inspection Interval Inservice Inspection Pressure Test Plan CNS-15-047, Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais)2015-05-15015 May 2015 Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais) CNS-15-022, Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities2015-03-16016 March 2015 Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage2014-09-25025 September 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage CNS-14-001, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage2014-01-13013 January 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage ML13085A0252013-03-21021 March 2013 Inservice Inspection Report for End of Cycle 20 Refueling Outage ML12195A3462012-07-10010 July 2012 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 18 Refueling Outage ML12125A2972012-05-0303 May 2012 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information ML1109806012011-04-0505 April 2011 Steam Generator (SG) Tube Inspection Report for End of Cycle 17 Refueling Outage Pursuant to Technical Specification (TS) 5.6.8 ML1102003222011-01-19019 January 2011 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0920104982009-07-14014 July 2009 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 16 Refueling Outage ML0927500082008-09-11011 September 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0805001792008-02-11011 February 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 15 Refueling Outage ML0732001122007-11-0808 November 2007 Request for Relief Number 07-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0721202212007-07-30030 July 2007 Notification of Inspection and Request for Information ML0713503782007-05-0707 May 2007 Submittal of Steam Generator Inservice Inspection Documentation for Third Ten-Year Interval ML0709502752007-03-28028 March 2007 Inservice Inspection Report for End of Cycle 16 Refueling Outage ML0623403632006-08-15015 August 2006 Inservice Testing (IST) Program for Pumps and Valves - Third Ten-Year Interval Plan ML0620603112006-07-18018 July 2006 Inservice Inspection Reports for End of Cycle 14 Refueling Outage ML0607403192006-03-0606 March 2006 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0603901542006-02-0606 February 2006 Notification of Inspection and Request for Information ML0525905642005-09-0808 September 2005 Request for Relief Number 05-CN-004 Limited Weld Examinations During End-of-Cycle 15 Refueling Outage ML0525004942005-08-30030 August 2005 Inservice Inspection Report and Steam Generator Outage Summary Report for End-of-Cycle 15 Refueling Outage ML0518601322005-06-16016 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0514002732005-05-11011 May 2005 Request for Relief Number 05-CN-003, Limited Volumetric Inspection Coverages During End-of-Cycle 12 and End-of-Cycle 13 Refueling Outages ML0508105992005-03-11011 March 2005 Duke Requests NRC Approval of an Alternative to the Requirements of the 1998 Edition Through the 2000 Addenda of the Pressure Vessel Code, Section XI for the Listed Inservice Inspection Intervals ML0502604532005-01-17017 January 2005 Inservice Inspection Report for End of Cycle 13 Refueling Outage ML0430103872004-10-19019 October 2004 Second Ten Year Inservice Inspection Interval Steam Generator C Hot Leg Nozzle Welds ML0414901162004-05-18018 May 2004 Request for Relief from Pressure Requirement at Certain Class 1 Inservice Inspection Pressure Test Boundaries ML0408502452004-03-17017 March 2004 Inservice Inspection Report for End-of- Cycle 14 Refueling Outage ML0317605962003-06-18018 June 2003 Inservice Inspection Report & Steam Generator Outage Summary Report for End of Cycle 12 Refueling Outage ML0313405102003-05-0707 May 2003 Relief, Request for Relief Number 02-002, Revision 1 Re Limited Weld Examinations for End of Cycle 13 Refueling Outage 2023-09-25
[Table view] |
Text
Duke DUKE ENERGY CAROLINAS, LLC Eueg Catawba Nuclear Station PlTEnergy, 4800 Concord Road Carolinas York, SC 29745 May 3, 2012 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information (TAC Nos. ME7277 through ME7283)
Reference:
Letter from Duke Energy to NRC dated September 28, 2011 The reference letter requested relief associated with limited weld examinations performed during the Unit 1 End-of-Cycle (EOC) 17 Refueling Outage (RFO), the Unit 1 EOC 18 RFO, and the Unit 2 EOC 16 RFO. On March 13, 2012, Requests for Additional Information (RAIs) were electronically received from the NRC. The purpose of this letter is to formally respond to these RAIs. The enclosure to this letter contains Duke Energy's response.
The format of the response is to restate each RAI question, followed by the response.This submittal document contains no regulatory commitments.
If there are any questions or if additional information is needed, please contact L.J. Rudy at (803) 701-3084.Very truly yours, George T. Hamrick Interim Site Vice President Enclosure 40(7 www. duke-energy, com U.S. Nuclear Regulatory Commission Page 2 May 3, 2012 xc (with enclosure):
V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.A. Hutto, III NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.H. Thompson (addressee only)NRC Project Manager (Catawba Nuclear Station)U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, DC 20555-0001 Enclosure Duke Energy Corporation Catawba Nuclear Station, Units I and 2 Relief Request #1 1-CN-001, Request for Additional Information NRC Request for Additional Information:
In the subject RR, the licensee seeks relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, for Catawba 1 and 2. The RR is requested for the remainder of the Third 1O-Year Inservice Inspection (ISI) Interval for Catawba 1 and 2 (ending on July 15, 2014, and August 19, 2016 for Catawba 1 and 2 respectively), in which the licensee adopted the 1998 Edition, with the 2000 Addenda, of Section XI of the ASME Code as the code of record for Catawba 1 and 2.In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a (g)(5)(iii), the licensee has submitted the subject RR for relief for limited examinations in multiple ASME Code Examination Categories.
The ASME Code requires that 100 percent of the examination volumes, or surface areas, described in ASME Code,Section XI, Tables IWB-2500-1, and IWC 2500-1 be performed during each interval.
The licensee stated that achieving inspection of 100 percent of the ASME Code-required volumes or surface areas is impractical at Catawba 1 and 2.The regulation at 10 CFR 50.55a (g)(5)(iii) states that when licensees determine that conformance with ASME Code requirements is impractical at their facility, they shall submit information to support this determination.
The NRC staff will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to the burden imposed on the licensee.The NRC staff has reviewed the information provided by the licensee in RR-CN-001and finds that the following additional information is needed to complete its review.For sections 2 through 12: 1. Discuss any indications found during the examinations and their disposition.
Duke Energy Response:
All indications detected during the examinations were the result of component geometry, were not associated with flaws in the component welds, and were acceptable without further evaluation.
The indications were dispositioned using procedure guidance of probe skewing, use of higher angles and indication plotting.For sections 6, 9, 10 and 12: 2. To determine the level of safety significance for each of the welds and/or attachments identify which system(s) would be impacted by a leak or failure. The enclosures to the subject RR provide this information for some of the welds and attachments, but not all.Duke Energy Response:
The requested information is provided in the response to Question #3.Duke Energy Corporation Catawba Nuclear Station, Units I and 2 Relief Request #11-CN-001, Request for Additional Information Enclosure
-Page 2 of 4
- 3. Provide a table or listing for each weld that lists the location and the systems.Duke Energy Response: This information is provided in the following table.Relief Weld ID System Location Flow Diagram Request Number Number Section (Copies Attached)Number 6.0 1NI11-9 Safety Injection (NI) Piping from Safety CN-1562-1.3 Injection Pumps 1A and 1B 9.0 ISGD-W261 Auxiliary Feedwater Steam Generator 1D CN-1592-1.1 (CA) Auxiliary Feedwater Nozzle to Transition Ring 10.0 1CA66-35 Auxiliary Feedwater Piping connecting to CN-1592-1.1 (CA) Steam Generator 1A Auxiliary Feedwater Nozzle 12.0 2NI70-4 Safety Injection (NI) Cold Leg "C" Piping CN-2562-1.3 connecting to Valve 2NI175 4. The components in these sections are described as constructed of stainless steel. Are any of the subject components described in these sections constructed of cast stainless steel?Duke Energy Response: No.5. The difficulty in obtaining volumetric coverage on several of the subject welds in these sections appears to be caused by use of fixed-angle probes with limited range available for scanning.
Provide a discussion on alternative examination methods and techniques that are qualified to ASME Code,Section XI, Appendix VIII (e.g., phase-array ultrasonic techniques (line scan or raster)), that cover many angles to be used to enhance the coverage of the subject welds described in these sections.Duke Energy Response: Use of manual or automated UT, phased array qualified under ASME Section Xi, Appendix VIII would not increase coverage due to the limitation created by the component configuration.
The use of any other technique available would incur the same physical scanning limitations.
Therefore, use of phased array or any other techniques, whether automated or manual, would obtain no additional coverage.Duke Energy Corporation Catawba Nuclear Station, Units I and 2 Relief Request #1 1-CN-001, Request for Additional Information Enclosure
-Page 3 of 4 For sections 4 and 5: 6. For the Heat Exchanger Head-to-Flange Weld #1 ELDHX-HD-FLG, Summary Number C1 .20.0003, it was noted that limitations were caused by the four physical scanning limitations, all located on the S2 head side. Describe in detail the four limitations that prevent performing the ASME Code-required examination.
Duke Energy Response: The limitations encountered on this weld were two 2" diameter and two 34" diameter nozzles in close proximity to, and on one side of, the 9-1/2" diameter heat exchanger head-to- flange weld. The nozzle welds completely covered the adjacent base material on the Surface 2 head up to the toe of the weld for a total length of 15 inches. The total weld length, including the limited inspection areas, is 30 inches.The NRC question requests that a response be provided for both sections 4 and 5. However, question 6 is specific to section 4, so a response for section 5 has not been provided.Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Relief Request #1 1-CN-001, Request for Additional Information Enclosure
-Page 4 of 4 I a 1 1. 1 11 1 11 1 il 1 1.I A I A I I In I A I IA I II I 12 I I~ I~yA 8 tl I i v l4 IL1x1ýT=ZD-a=A* _A-TrAC, ATA-i 20ACI. 1A"'I~'T'khtLWhI-h
-,ja -om am -V MINII A fls mll IAYISI -Wsat a".st KIW O CN- 1562-01 83 [ED~14 A (ýJ.-I S14 k7V o CA CONDITION 2 CA CONDITION I L I a3 0 gggg~a WhIN~AI~0.1.15AflAO FLOW l 03015 OF SAM limII) ST--* I A I A A I A I A I ' I A I .1 I IA I Sl IS I hA I CI
- i It + i J I 1 1 12 1 13 1 14 ,,i 10WO NO 4rrno159-1 1 19 h I t h-1 Li f-~' 25C~-SI, ~~aEi I L --.JI 1424 C3=4-I I-+-i -c.[4- -A --÷ i _<-4 IL~ ~C9-~ -+-9i:2: f= !-v C3:)-. H aNO~---~- Q w-@-C I -mm;- h-C;a
- Ha -~r P, 6wS CL4 : S*G i I-IH I I-~z C:"-c 5-- I~1A= C~OCO n&c P) --t .- T,- p Ptr I; R -! 1 a CA- .10-AAAAuL2t
'iHIu GA CONDITION 4 GA CONDITION I 0ý9 _PVý4Ft 1 1 1. 1 1 1CTLý m ,1 Fo W 10011,01OF UXKI01 FEOAE II~flf4H11AIiiil~t
'7H'~FIMTE4 II CAI-r-w _______________
A ITM I -I ý-- I I 3 4 b a .8, ...'11 .ý 0 --, & -1 2 1 b I 10 1 II 2u. 1 I A OR=M-140 EO aen CNOOA PEI 2 a 1 SM 1 o I I I -- "- .53 1 54 1 A.An.aOa.u.
an A n.m A a Af-Ala- -Al.-J9--AA.~~A ~ AMAW.~-6:o~~C=10A-CIE=a i 1..KAV~A~ CN-3NK2-I 3 I K H~i:L N[A.NaI0~ -~;r3 T~sro~ 1*K CATPns~~t3A AX3CLC7NAT~
~'T1aVr7 ~fZa~LL~ ~ o 1.50.I at a E1~m ~Cal K odoA M w~fa"i-n.KI~Le~I i -.D Itt Y., t .... \GA CONDITONZ SI DAAAA n~aAO CONDITION I ft ~ ~ ~ ~ i I t A AS A AMAASMQIIA MJ= 5CtEO r NCIAI IT 2 II I allt I 4 kOSIIA AAAA~t MA A AN CN-25627-I13 2 1 3 1 a I-I I c Ij i j, i