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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML21102A3582021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 10, Steam and Power Conversion NRC-2021-0009, Update to Final Safety Analysis Report, Chapter 2, Site and Environment2021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 2, Site and Environment ML21102A3512021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix D, Diesel Generator Project ML21102A3532021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix C, Purpose of Chemical Addition to Containment Spray ML21102A3572021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix T, Technical Requirements Manual ML21102A3492021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems ML21102A3442021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 3, Design Basis ML21102A3462021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 15, Aging Management Programs and Time Limited Aging Analysis ML21102A3502021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix I, 10CFR50, Appendix I Evaluation of Radioactive Releases from Point Beach Nuclear Plant (Historical) - ML21102A3562021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix a, Station Blackout (SBO) ML21102A3472021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 12, General ML21102A3452021-04-0202 April 2021 Update to Final Safety Analysis Report, List of Effective Pages ML21102A3542021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 14, Safety Analysis ML21102A3432021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21102A3402021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML21102A3552021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 5, Containment System Structure ML21102A3412021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 13, Site Surveillance and Testing Programs (Historical) ML21102A3482021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 7, Instrumentation and Control ML21102A3522021-04-0202 April 2021 Update to Final Safety Analysis Report, Appendix B ML21102A3422021-04-0202 April 2021 Submittal of Periodic Update of the Final Safety Analysis Report ML21102A3392021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 4, Design Basis ML21102A3382021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 11, Waste Disposal Systems and Radiation Protection ML21102A3362021-04-0202 April 2021 Update to Final Safety Analysis Report, Chapter 8, Introduction to the Electrical Distribution Systems NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2018-0030, Construction Truss License Amendment Request 278 Draft Updated Final Safety Analysis Report (UFSAR) Revision2018-05-29029 May 2018 Construction Truss License Amendment Request 278 Draft Updated Final Safety Analysis Report (UFSAR) Revision ML18130A0902018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix C.1, Purpose of Chemical Addition to Containment Spray ML18130A0922018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix I.1, 10CFR50, Appendix I Evaluation of Radioactive Releases from Point Beach Nuclear Plant ML18130A0912018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix D, Diesel Generator Project ML18130A0822018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 10, Steam and Power Conversion ML18130A0862018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 14, Safety Analysis ML18130A0852018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 13, Site Surveillance and Testing Programs (Historical) ML18130A0772018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 5.0, Containment System Structure ML18130A0732018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 1.0, Introduction and Summary ML18130A0782018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 6.0, Engineered Safety Features ML18130A0752018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 3.0, Design Basis ML18130A0792018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 7.0, Instrumentation and Control ML18130A0812018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 9.0, Auxiliary and Emergency Systems ML18130A0742018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 2.0, Site and Environment ML18130A0832018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 11, Waste Disposal Systems and Radiation Protection ML18130A0762018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 4.0, Design Basis ML18130A0872018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 15, Aging Management Programs and Time Limited Aging Analysis ML18130A0722018-05-0202 May 2018 Update of Final Safety Analysis Report, List of Effective Pages ML18130A0372018-05-0202 May 2018 Submittal of 2017 Update of Final Safety Analysis Report ML18130A0882018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix A.1, Station Blackout (SBO) ML18130A0892018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix B.2, Design Parameters and Plant Comparisons NRC 2018-0016, Update of Final Safety Analysis Report, Appendix T, Technical Requirements Manual2018-05-0202 May 2018 Update of Final Safety Analysis Report, Appendix T, Technical Requirements Manual NRC 2018-0016, Point Beach Nuclear Plant, Units 1 & 2, Submittal of 2017 Update of Final Safety Analysis Report2018-05-0202 May 2018 Point Beach Nuclear Plant, Units 1 & 2, Submittal of 2017 Update of Final Safety Analysis Report ML18130A0802018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 8.0, Introduction to the Electrical Distribution Systems ML18130A0842018-05-0202 May 2018 Update of Final Safety Analysis Report, Chapter 12, General ML16251A1662016-09-0101 September 2016 Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis 2021-04-02
[Table view] |
Text
Security Related Information
-Withhold from Public Disclosure Under 10 CFR 2.390 NEXTera ENERGY,&
POINT BEACH May 2, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Periodic Update of the Final Safety Analysis Report NRG 2018-0016 10 CFR 50. 71 (e) 10 CFR 54.37(b)
In accordance with the requirements of 10 CFR 50.71(e) and 10 CFR 54.37(b),
this letter submits a periodic update of the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). Enclosure 1 to this letter includes 1 DVD-HOM containing the non-public version of the Point Beach FSAR, including the description of changes.
The FSAR is being submitted in its entirety, constituting a total replacement copy. Enclosure 1 contains security related information as defined by 10 CFR 2.390(d) and should be withheld from public disclosure.
The enclosure reflects changes since the last periodic update of September 1, 2016. Enclosure 2 to this letter includes 1 DVD-ROM containing the public version of the Point Beach FSAR. Enclosure 3 to this letter includes a report describing how the effects of aging of newly-identified structures, systems or components (SSCs) will be managed, as required by 10 CFR 54.37(b).
This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.
Security Related Information
-Withhold Under 10 CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.
NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241 Security Related Information
-Withhold from Public Disclosure Under 10 CFR 2.390 Document Control Desk Page 2 I declare under penalty of perjury that this submittal accurately presents changes made since the previous submittal that reflect information and analyses submitted to the NRG or prepared pursuant to NRG requirements, and changes made under the provisions of 1 O CFR 50.59. Executed on May 2, 2018. Sincerely,
~:;::;B2C
___ _ Robert Craven Plant General Manager Enclosures (3) cc: Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW (less enclosures)
Security Related Information
-Withhold Under 10 CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.
Security Related Information
-Withhold from Public Disclosure Under 10 CFR 2.390 ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2017 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT NOT FOR PUBLIC DISCLOSURE Security Related Information
-Withhold Under 10 CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.
~** ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2017 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT REDACTED
-PUBLIC VERSION ENCLOSURE 3 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REPORT CONSISTENT WITH 10 CFR 54.37(b)
ON HOW EFFECTS OF AGING OF NEWLY-IDENTIFIED STRUCTURES,
- SYSTEMS, OR COMPONENTS ARE MANAGED This update follows the guidance regarding the appropriate level of detail for reports under 10 CFR 54.37(b) that is presented in Frequently Asked Questions (FAQs) About License Renewal" Inspection Procedure (IP) 71003, "Post-Approval Site Inspection for License Renewal."
This report provides summary information as required by 1 O CFR 54.37(b) for the period between July 15, 2016 through March 30, 2018. Regulatory Requirements and Guidance 10 CFR 54.37(b)
After the renewed license is issued, the FSAR update required by 10 CFR 50.71(e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analysis in. accordance with §54. 21. This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation.
RIS 2007-16, Revision 1 Newly Identified Systems.
Structures.
and Components (SSCs) The intent of 10 CFR 54.37(b) is to capture those SSCs that, if they had been identified at the time of the license renewal application, would have been subject to an aging management review or evaluation of TLAAs. In the context of 10 CFR 54.37(b),
newly identified SSCs that should be included in the next FSAR update required by 10 CFR 50. 71(e) are those SSCs that meet one of the two following conditions:
Page 1 of 2 (1) There is a change to the current licensing basis (GLB) that meets the following criteria:
The change impacts SSGs that were not in scope for license renewal when the NRG approved the license renewal application.
The SSGs would have been in the scope of license renewal based on the GLB change if 10 GFR 54.4(a) were applied to the SSGs. (2) SSGs were installed in the plant at the time of the license renewal review that, in accordance with the GLB at the time, should have been included in the scope of license renewal per 1 O GFR 54. 4( a) but were not identified as in scope until after issuance of the renewed license.
SSGs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions of 10 GFR 54.37(b).
Identification of SSGs under 10 GFR 54.37(b)
The language of 10 GFR 54.37(b) does not limit how or who finds newly identified SSGs. A licensee may identify SSGs that should be within the scope of its license renewal program at any time. The NRG staff may also discover newly identified SSGs. One way to identify these SSGs is through the LR-ISG process.
Newly Identified SSC
- 1n 2018, using the guidance of RIS 2007-16, Rev. 1, PBNP staff reviewed changes to the plant that had taken place since the last 54.37(b) review of the Current Licensing Basis (July 2016). This review identified 143 components that would be considered "newly identified" and subject to 10 CFR 54.37(b) reporting requirements.
Of these 143 components, 136 are associated with existing plant components that are now being credited for NFPA-805.
The remaining 7 are components that are now being credited for flood mitigation.
117 of the 143 are Active components, not requiring aging management.
The remaining 26 are passive, long lived components (doors, valves, pumps) are already represented within the aging management tables submitted with the PBNP LRA. These 26 passive, long-lived components have been evaluated and assigned to existing Aging Management Programs as required.
Appropriate aging. management strategies have been invoked to adequately detect and manage the applicable aging effects throughout the period of extended operation.
A list of tlie 143 newly identified components is not"provided in this document, consistent with the level of detail provided in the LRA. Page 2 of 2 May 2, 2018 Document Control Desk U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08H 4A 11555 Rockville Pike Rockville, MD 20852~2'738 Manual: FSAR Manual No.: . 80 Issue Date: May 2, 2018 1. UFSAR 2017 Update. AFTER UPDATING YOUR MANUAL, PLEASE SIGN AND RETURN THIS RECEIPT ACKNOWLEDGMENT TO: POINT BEACH NUCLEAR PLANT, DISTRIBUTION CENTER, 6590 NUCLEAR ROAD, TWO RIVERS, WI 54241. If you have any questions, please call Document Control at ext. 7638. ********Special Distribution Notes********
1-Public CD and 1-Non-Public CD Distribution Center -PBNP Date ----------------