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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter 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 IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22257A0132022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22257A0052022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22257A0062022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22251A3672022-09-0808 September 2022 Submittal of Updated Final Safety Analysis Report, Cover Letter ML22257A0422022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22257A0432022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22257A0092022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 4, Reactor ML22257A0072022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 6, Engineering Safety Features ML22257A0172022-09-0808 September 2022 Updated Final Safety Analysis Report, Appendix a, Updated Final Safety Analysis Report Supplement ML22257A0182022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 18, Responses to TMI-Related Requirements ML22257A0272022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22257A0392022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control Systems ML22257A0372022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22257A0202022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22257A0302022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 18, Responses to TMI-Related Requirements ML22257A0322022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22257A0112022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22257A0162022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22257A0212022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22257A0152022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control Systems ML22257A0142022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22257A0252022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22257A0102022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML22257A0222022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22257A0232022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22257A0362022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 4, Reactor ML22257A0332022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22257A0282022-09-0808 September 2022 Updated Final Safety Analysis Report, Appendix a, Updated Final Safety Analysis Report Supplement ML22257A0262022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML22257A0402022-09-0808 September 2022 Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22073A1862022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22073A1772022-03-0808 March 2022 Updated Final Safety Analysis Report, Affected Pages ML22073A1762022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control Systems ML22073A1752022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22073A1782022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22073A1732022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22073A1722022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML22073A1712022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 4, Reactor ML22073A1692022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22073A1672022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22073A1822022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 18, Responses to TMI-Related Requirements ML22073A1832022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22073A1842022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22073A1852022-03-0808 March 2022 Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML21039A2562021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML21039A2592021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 4, Reactor ML21039A2652021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control Systems ML21039A2552021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 8, Electric Power ML21039A2512021-01-27027 January 2021 Submittal of Updated Final Safety Analysis Report ML21039A3202021-01-27027 January 2021 Updated Final Safety Analysis Report, Chapter 8, Electric Power 2022-09-08
[Table view] |
Text
'~'Ente-rgy Entergy R0. Box 756 Port Gibson, MS 39150 Tel 601 437 6409 George A. Williams Vice President -Operations Grand Gulf Nuclear Station July 01, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Document Control Desk
Subject:
UFSAR Update for Grand Gulf Nuclear Station dated June 2003 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29
Reference:
NRC REGULATORY ISSUE
SUMMARY
2001-05 GUIDANCE ON SUBMITTING DOCUMENTS TO THE NRC BY ELECTRONIC INFORMATION EXCHANGE OR ON CD-ROM GNRO-2003/00040 Ladies and Gentlemen:
Pursuant to 10CFR50.71 (e) and in accordance with the 10CFR50.4 exception granted by the above reference, Entergy Operations, Inc. hereby submits only one CD-ROM copy of the current Updated Final Safety Analysis Report (UFSAR). The UFSAR CD-ROM (electronic copy) is a complete copy of our 10CFR50 Appendix B (Section VI Document Control) Controlled Copy of the UFSAR and includes recent revisions. A file is included on the CD-ROM called "prindex.pdf' which is a page revision index. The page revision index identifies the current pages of the FSAR following page replacement. The page revision index has the changed pages highlighted in BLUE and BOLDED and is included as an aidfor NRC reviewers.
GGNS now submits UFSAR updates on a more frequent basis than that required by 10CFR50.71(e). This change has been made to improve the timeliness of information provided to the NRC and to take advantage of recent changes made by the NRC in the area of electronic transmittal of information. Attachment 1 provides a detailed explanation of the CD-ROM technical details.
f~~ 0 2
July 01 2003 GNRO-2003/00040 Page2 of 2 This UFSAR update includes the designation of certain information as historical and the removal of certain redundant information pursuant to the guidance of NEI-98-03 Rev. I as endorsed by the NRC in Regulatory Guide 1.181. These changes are described in Attachment 2.
I hereby certify, to the best of my knowledge, information and belief, that the information provided in the attached UFSAR meets the requirements of 10CFR50.71 (e) to update the UFSAR to reflect all changes to a maximum of six months prior to the date of this submittal. This letter does not contain any commitments.
Should you have any questions, please contact James Owens at 601-437-6219.
Yo rs truly, GAW/JE .jeo attachments: 1. GGNS UFSAR CD-ROM TECHNICAL DETAILS
- 2. FSAR-only Changes enclosure: One CD-ROM copy of the Complete 10CFR50 Appendix B Controlled Copy Updated Final Safety Analysis Report cc:
Hoeg T. L. (GGNS Senior Resident) (w/a)*
Levanway D. E. (Wise Carter) (wla)*
Reynolds N. S. (wla)*
Smith L. J. (Wise Carter) (wla)*
Thomas H. L. I__ (w/o)
- w/o enclosure U.S. Nuclear Regulatory Commission ATTN: Mr. Thomas P. Gwynn Acting Regional Administrator 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/7D-1 Washington, D.C. 20555-0001
July 01, 2003 GNRO-2003/00040 bcc:
OUTLOOK MAIL: DISTRIBUTION IS ALL ELECTRONIC Ashley G. R. (ANO-NSAPL) wia Green R. L. (GG-TRNG) w/a Bottemiller C. A. (GG-NSAPL) w/a Cotton S. R. (ANO-NSA) w/a Williams G. A (GG-VP) wla Edwards J. B. (GG-GMPO) w/a GGN CENTRAL FILE (10) w/a GGN PLANT LICENSING w/a King R. J. (RB-NSA) w/a Krupa M. A. (ECH-NSL) w/a Leavines J. W. (RB-NSAPL) w/a Ridgel J. A. (W3-NSAPL) w/a Roberts J. C. (GG-NSA) w/a Wiles D. P. (GG-ENG) w/a Note: enclosure not included OTHER: File (LRS.DOCS Directory - GNRI or GNRO) f
ATTACHMENT I TO GNRO-2003/00040 GGNS UFSAR CD-ROM TECHNICAL DETAILS
Attachment 1 to GNRO-2003/00040 Page 1 of 2 UFSAR CD-ROM TECHNICAL DETAILS The UFSAR CD-ROM can be accessed directly from the CD-ROM or can be loaded on local area network for multi-user access. The following information is provided explaining the content of the CD-ROM:
- The file format chosen is PDF; however, two types PDF file formats are included: PDF ORIGINAL IMAGE with HIDDEN TEXT or PDF NORMAL. The majority file format used is PDF ORIGINAL IMAGE with HIDDEN TEXT. This means the document was created by scanning the original paper copy of the document This PDF scanned image was further processed, using ADOBE ACROBAT, by performing an OCR (optical character recognition) of the scanned image to allow text search capability.
The PDF scanned image of the UFSAR hardcopy is preserved and the OCR text is hidden behind the image. There are a couple of files on the CD-ROMthat use the PDF NORMAL format The PDF NORMAL file was electronically created using the word processing native file.
- The software used to view the UFSAR is located in the root directory of the CD-ROM and is ADOBE ACROBAT READER 3.01 or 4.05. The names of the files are "rs32e301.exe" or rs4O5eng.exe" and it is self-executing file. When executed it will load a copy of ADOBE ACROBAT READER 3.01 on your hard drive. This will allow you to keyword search the entire UFSAR and view/print all PDF files on the CD-ROM More information concerning free use of the supplied software is located at:
http://www.adobe.com/products/acrobat/readennain.hmln.
- Once the reader is loaded, use the reader software to open the "START. PDF" file located on the CD-ROM. After the file is loaded, a picture of the Grand Gulf Nuclear Station site will be seen. Selecting the red box identifed as Table of Contents on the opening screen will load the UFSAR Table of Contents. Each chapter can be accessed by selecting the highlighted box around the chapter name. If you wish totext search the entire UFSAR, select this icon:
- A help file is available on the CD-ROM called "help.pdf'. It provides additbnal guidance on usage of the UFSAR CD-ROM.
- The CD-ROM UFSAR file structure is set-up to replicate the HARDCOPY books of the UFSAR, which includes tabbing and numbering of chapter and subchapters. Each subchapter is complete and includes all text, figures, and tables. This includes 8.5xl 1" and 1x17" sheets normally found in the HARDCOPY books.
- The UFSAR on the CD-ROM is setup such that it can be easily placed on a local area network by copying the entire "UFSARIMA" direcbr onto the network drive. Once on the network, ADOBE ACROBAT READER should be used to self load the file named "bltoc.pdf" file or "start.pdf'file.
Attachment I to GNRO-2003/00040 Page 2 of 2
- The UFSAR CD-ROM file structure is as follows:
AI~~~ddrn J~~~~~~lsof R~W:S-0CSFSAIMAW.ha4 UW4 nsmn kNm Si,. Tmbcmwe ch1lc 272KB 5/26maloPm A6*beAcaoa..
2WS 1/27/99651 PM
.1 chl.8 Adc~obeb..
1/279 1 51 PM
' chapIl3 511KB AdobeAcwob.. 1/27/99650 PM AdobeAcm.. 1/27M9SOPM Es-.jchaptl4 :i chi 5 1/99:50 PM BEE c4M15 531KB 5/5/99 531 PM 1.119KB Adobe Acr*. 51/00 20M PM
.1 Ch.5 6.455ZB 52600117PM
-.2J chapt2 629KB 5ASM 217 PM AdoeAmob,.
ER I hwO3 45WB 1/27M96.49 PM
- Each chapter can be directly accessed by using the reader software. This is advantageous if comparisons of different chapters are necessary.
ATTACHMENT 2 TO GNRO-2003/00040 FSAR-ONLY CHANGES (NEI-98-03)
NEI-98-03 FSAR CHANGES FSAR 98-03 Type of Change I Justification for Change Page/Table/ Description of Change Figure (Licensing Document Change Number)
Page 7.7-56 Removal of excessive detail This change removes excessive detail regarding (LDC 03028) Change UFSAR Section 7.7.10.3.4, 2nd the specific spans of the offgas system andan3rdsetnet ea:"w sentence to read: "Two lwinstrumentation.
flow Theseas and may again change spans have changed, instrumentation is range measurements are made, the low upgraded, and the specific range/span flow or normal plant operation range, and information provides no additional understanding the high flow or startup range." d to the reader, nor does its removal change the intent or information presented in the passage in a manner that would affect the readers understanding of the system.
NRC SUBMITTAL REVIEW Letter# I GNRO-2003/00040 I Response Due: I N/A I
Subject:
UFSAR UPDATE FOR GRAND GULF NUCLEAR STATION DATED JUNE 2003 I Correspondence Preparer i phone #: James Owens /437-6219 I SECTION I LETTER CONCURRENCE and AGREEMENT TO PERFORM ACTIONS (see Section 111)
Responsible Concurrence DepartmenVPosition (sign, interoffice memo, e-mall, or telecom)
NSA - PL k't4114 &c AY 4 COMMENTS SECTION II CORRESPONDENCE SCREENING Does this letter contain commitments? If "yes," identify the commitments with Yes L due dates in the submittal and in Section I. No X Does this letter contain any information or analyses of new safety issues performed Yes L at NRC request or to satisfy a regulatory requirement? If "yes," reflect No X requirement to update the UFSAR in Section I.
Does this letter request NRC approval of a change that may/will require UFSAR, TS Yes L Bases, or other Licensing documents to be updated if approved? If "yes," reflect No X requirement to update the applicable Licensing document in Section I..
Does this letter require procedure changes, if approved? If "yes,"f indicate in Yes LI Section I an action to determine affected procedures. (The Correspondence No X Preparer may indicate the specific procedures requiring revision, if known.) _
Does this letter contain information certified accurate? If "yes," identify the Yes LI information and document certification in an attachment. (Attachment 9.6 may No X be used.)
SECTION ACTION ITEMS Required Actions Due Date RESPONSIBLE NOTE: Actions needed upon approval should be captured inthe DEPARTMENT appropriate action tracking system.
CERTIFICATION PLANT LICENSING SECTION IV FINAL DOCUMENT SIGNOFF FOR SUBMITTAL Correspondence __
Prreprence Final Peer Review (optional) A//-
Responsible Dept. Head I
CERTIFICATION REFERENCE Document Number: I GNRO-2003100040 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I Document DescriptionlTitle: GNRO-2003/00040 - UFSAR UPDATE FOR GRAND GULF NUCLEAR STATION DATED: June 2003 The LDCs listed below are included in this submittal and provide certification and technical justifications for each change.
Certifiable Statement(s): (Identify location in submittal adequate; e.g., page3, para2, sentl OR paste in words of statement.)
ALL Objective Evidence or Peer Review:
used)
(List pertinent documents and sections OR give basis for peer review. Indicate NA' if not
]
LDCs:
2000055 2000063 2001032 2001150 2001169 2001193 2002023 2002035 2002046 2002063 2002080 2002131 2002136 2002137 2002138 2002141 2002144 2002147 2002149 2002150 2002154 2003002 2003005 2003011 2003012 2003015 2003017 2003018 2003021 2003022 2003023 2003024 2003026 2003028 2003030 2003031 2003032 2003036 2003040 4- t 4- 4.
4- 4.
- 4. 4-
- 4. 4-1- 1*
Preparer:
James E. Owens NSA-Plant Licensing July 01, 2003 Name Department Date Peer Reviewer: (Indicate N/A" if not used)
Name Department I Dbate