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Category:Letter
MONTHYEARML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24149A1592024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24087A1962024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close IR 05000416/20220042024-03-19019 March 2024 – Amended Integrated Inspection Report 05000416/2022004 and Exercise of Enforcement Discretion ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 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)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) 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 2024-09-09
[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] |
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'~'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