NLS2017035, Updated Safety Analysis Report Revision Xxviii

Updated Safety Analysis Report Revision Xxviii

ML17117A282
Person / Time
Site:	Cooper
Issue date:	04/24/2017
From:	Higginbotham K Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2017035
Download: ML17117A282 (26)

Text

H Nebraska Public Power District Always there when you need us NLS2017035 50.71(e)

April24,2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

• 20555-0001

Subject:

Updated Safety Analysis Report Revision XX.VIII Cooper Nuclear Station, Docket No. 50-298, DPR-46

Dear Sir or Madam:

The purpose of this letter is to submit the twenty-eighth revision of the Cooper Nuclear Station (CNS) Updated Safety Analysis Report (USAR), in accordance with the provisions of 10 CPR 50.71(e). This revision covers the reporting cycle from March 11, 2015, through February 24, 2017.

This is the first CNS USAR revision being submitted electronically on CD-ROM on a total replacement basis. Changes made during this reporting cycle can be identified by revision dates during the time period noted above, along with corresponding revision bars. Attachment 1 provides a listing of the document components included on each of the six enclosed CD-ROMs.

The following documents are incorporated in the USAR by reference and do not have a separate regulatory requirement for reporting of changes. Therefore, updated versions of these documents are provided on the enclosed CD-ROMs in accordance with the provisions of 10 CPR 50.71(e).

• CNS Technical Requirements Manual Limiting Conditions for Operation

• Inservice Inspection Program for Cooper Nuclear Station (This document was previously submitted per NLS2016013 on April 8, 2016, in hardcopy; however, a complete electronic version is enclosed.)

• Plant Unique Analysis Report (There were no changes to this document; however, a complete electronic version is enclosed.)

• Selected Controlled Station Drawings The CNS USAR has been reviewed for security-related information, as discussed in Regulatory Issue Summary 2015-17. As a result, Nebraska Public Power District is submitting both a non-public version (Enclosures 1, 2A & 2B) and a public version with security-related information removed (Enclosures 3, 4A & 4B).

EnclOsures 1, 2A, and 2B transmitted herewith contain Security-Related Information.

When separated from these enclosures, this transmittal document is decontrolled.

COOPER NUCLEAR STATION P.O. Box 98 /Brownville, NE 68321-0098 Telephone: (402) 825-3811 /Fax: {402} 825-5211 www.nppd.com

NLS2017035 Page 2 of3 As specified by Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," a summary listing ofUSAR deletions made during this reporting period is included as Attachment 2.

In accordance with NEI 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," a summary of commitment changes made during this reporting period is provided in .

Pursuant to the requirements of 10 CPR 50.4 and guidance for electronic submissions to the U.S.

Nuclear Regulatory Commission (NRC), copies are being provided to the NRC Region IV Office and the NRC Resident Inspector for CNS.

This letter contains no commitments.

If you have any questions regarding this submittal, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

I declare under penalty of perjury that the foregoing is true and correct.

Executed On: .q/.;_q 1

b7 D'te Sin.?/

/~

Kenneth Higginbotham Vice President-Nuclear and Chief Nuclear Officer

/lb Attachments: 1 - List of Document Components on CD-ROMs 2 - Summary of USAR Deletions 3 - Summary of Regulatory Commitment Changes Enclosures 1, 2A, and 2B transmitted herewith contain Security-Related Information.

When separated from these enclosures, this transmittal document is decontrolled.

NLS2017035 Page 3 of3

Enclosures:

1 - USAR Revision XXVIII and Additional Documents Incorporated by Reference, Non-Public Version (on CD-ROM) 2A- Station Drawings Incorporated in the USAR by Reference, Non-Public Version (on CD-ROM, 1 of2) 2B - Station Drawings Incorporated in the USAR by Reference, Non-Public Version (on CD-ROM, 2 of2) 3 - USAR Revision XXVIII and Additional Documents Incorporated by Reference, Public Version (on CD-ROM) 4A - Station Drawings Incorporated in the USAR by Reference, Public Version (on CD-ROM, 1 of 2) 4B - Station Drawings Incorporated in the USAR by Reference, Public Version (on CD-ROM, 2 of2) cc: Regional Administrator, w/Attachments and Enclosures 1, 2A, 2B USNRC - Region IV Cooper Project Manager, w/Attachments and Enclosures 1, 2A, 2B USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector, w/Attachments and Enclosures 1, 2A, 2B (2 copies)

USNRC-CNS Institute of Nuclear Power Operations, w/Enclosures 3, 4A, 4B Emergency Management NPG Distribution, w/o Attachments and Enclosures CNS Records, w/Attachments and Enclosures Enclosures 1, 2A, and 2B transmitted herewith contain Security-Related Information.

When separated from these enclosures, this transmittal document is decontrolled.

NLS2017035 Attachnient 1 Page 1 of 14 LIST OF DOCUMENT COMPONENTS ON CD-ROMS CD-ROMN0.1 USAR REVISION XXVIII AND ..

ADDITIONAL DOCUMENT~ INCORPORATED BY REFERENCE NON-PUBLIC VERSION File Name 001 - USAR List of Effective Pages.pdf 002 - USAR Table of Contents.pdf 003 - USAR List ofFigures.pdf 004 - USAR List of Tables.pdf 005 - USAR Section l .pdf 006 - USAR Section 1 Figures.pdf 007 - USAR Section Il.pdf 008 - USAR Section II Figures.pdf 009 - USAR Section III.pdf 010 - USAR Section III Figures.pdf 011 - USAR Section IV.pdf 012 - USAR Section IV Figures.pdf 013 - USAR Section V.pdf 014 - USAR Section V Figures.pdf 015 - USAR Section Vl.pdf 016 - USAR Section VI Figures.pdf 017 - USAR Section VII.pdf 018 - USAR Section VII Figures.pdf 019 - USAR Section VIII.pdf 020 - USAR Section VIII Figures.pdf 021 - USAR Section IX.pdf 022 - USAR Section X.pdf 023 - USAR Section X Figures.pdf 024 - USAR Section Xl.pdf 025 - USAR Section XII.pdf 026 - USAR Section XIII.pdf 027 - USAR Section XIII Figures.pdf 028 - USAR Section XIV.pdf 029 - USAR Section XIV Figures.pdf 030 - USAR Appendix A.pdf 031 - USAR Appendix B. pdf 032 - USAR Appendix C.pdf 033 - USAR Appendix C Figures.pdf 034 - USAR Appendix D.pdf 035 - USAR Appendix D(l).pdf 036 - USAR Appendix D(l) Figures.pdf 037 - USAR Appendix E. pdf 038 - USAR Appendix F.pdf

NLS2017035 Attachment 1 Page 2of14 CD-ROM NO. 1 CONTINUED

,_039 - USAR Appendix G.pdf t-040 - USAR A endix G Figures.pdf

,_041 - USAR Appendix H.pdf

,_042- USAR A pendix J.pdf t-043 - USAR Appendix K.pdf t-044 -Tech Req Manual Section 3.pdf

,__045 - ISI Program Document. df

~

046 - Plant Unique Analysis Report.pdf

NLS2017035 Page 3of14 CD-ROM NO. 2A STATION DRAWINGS INCORPORATED IN THE USAR BY REFERENCE NON-PUBLIC VERSION File Name OOI - Drawing I I 7C3346.pdf 002 - Drawing I I 7C3349.pdf 003 -Drawing I6IF282BC SHl.pdf 004 - Drawing 197R567 SHI .pdf 005 -Drawing 197R576 SHl.pdf 006 - Drawing 2001 SHI .pdf 007 - Drawing 200I SH2.pdf 008 -Drawing 2002 SHI.pdf 009 - Drawing 2002 SH2.pdf 010 - Drawing 2004 SHl.pdf OI I - Drawing 2004 SH2.pdf OI2 -Drawing 2004 SH3.pdf 013 -Drawing 2006 SHl.pdf OI4 -Drawing 2006 SH2.pdf OI5 -Drawing 2006 SH3.pdf OI6 -Drawing 2006 SH4.pdf OI 7 - Drawing 2007.pdf OI8 -Drawing 2009.pdf OI9 - Drawing 20IO SHl.pdf 020 - Drawing 2010 SHIA.pdf 02I - Drawing 2010 SH2.pdf 022 - Drawing 2010 SH3.pdf 023 -Drawing 20IO SH4.pdf 024 - Drawing 2010 SH5.pdf 025 - Drawing 20I2 SH3.pdf 026 -Drawing 20I6 SHl.pdf 027 - Drawing 20I6 SHIA.pdf 028 - Drawing 20I6 SHIB.pdf 029 -Drawing 20I6 SHIC.pdf 030 - Drawing 20I 7.pdf 03I - Drawing 20I8.pdf 032 - Drawing 20I9 SHl.pdf 033 -Drawing 2019 SH2.pdf 034 - Drawing 2020.pdf 035 - Drawing 2021.pdf 036 - Drawing; 2026 SHI .pdf 037 - Drawing 2027 SHI .pdf 038 - Drawing 2027 SH2.pdf 039 - Drawing 2028.pdf 040 - Drawing 2030 SHI .pdf 04I - Drawing 2030 SH2.pdf

NLS2017035 Page 4of14 CD-ROM NO. 2A CONTINUED 042 - Drawing 203 I SHI .pdf 043 - Drawing 203 I SH2.pdf 044 - Drawing 203 I SH3.pdf 045 - Drawing 2032 SHI .pdf 046 -Drawing 2032 SH2.pdf 047 -Drawing 2032 SH3.pdf 048 - Drawing 2032 SH4.pdf 049 - Drawing 2032 SH5.pdf 050 - Drawing 2033 SHI .pdf 05I -Drawing 2033 SH2.pdf 052 - Drawing 2033 SH3.pdf 053 - Drawing 2033 SH4.pdf 054 - Drawing 2034.pdf 055 - Drawing 2035 SHI .pdf 056 - Drawing 2035 SH2.pdf 057 - Drawing 2035 SH3.pdf 058 - Drawing 2035 SH4.pdf 059 - Drawing 2036 SHI .pdf 060 - Drawing 2037.pdf 06I - Drawing 2038 SHI .pdf 062 -Drawing 2039.pdf 063 -Drawing 2040 SHl.pdf 064 -Drawing 2040 SH2.pdf 065 - Drawing 2042 SHI .pdf 066 - Drawing 2042 SH2.pdf 067 -Drawing 2042 SH3.pdf 068 -Drawing 2043.pdf 069 - Drawing 2044.pdf 070 - Drawing 2045 SHI .pdf 07I - Drawing 2045 SH2.pdf 072 - Drawing 2049 SH3.pdf 073 - Drawing 2050.pdf 074 - Drawing 2051.pdf 075 - Drawing 2052.pdf 076 - Drawing 2053.pdf 077 - Drawing 2054.pdf 078 - Drawing 2056.pdf 079 -Drawing 2059.pdf 080 - Drawing 2060.pdf 081 - Drawing 2061.pdf 082 - Drawing 2062.pdf 083 - Drawing 2063.pdf 084 - Drawing 2064.pdf 085 - Drawing 2065.pdf 086 - Drawing 2066.pdf

NLS2017035 Page 5of14 CD-ROM NO. 2A CONTINUED 087 - Drawing 2067 .pdf 088 - Drawing 2068. df 089 -Drawing 2069.pdf 090 -Drawing 2072.pdf 091-Drawing2073.pdf 092 - Drawing 2079 SHl .pdf ~~~~~~~~~~~~~~~~~~~~~~----l 093 - Drawing 2079 SH2.pdf ~~~~~~~~~~~~~~~~~~~~~~____,

094 - Drawing 2080.pdf 095 - Drawing 2084.pdf 096 - Drawing 2298.pdf 097 - Drawing 3001. df

NLS2017035 Page 6of14 CD-ROM NO. 2B STATION DRAWINGS INCORPORATED IN THE USAR BY REFERENCE NON-PUBLIC VERSION File Name 101 - Drawing 3005 SH4.pdf 102 - Drawing 3006 SH5.pdf 103 - Drawing 3007 SH6.pdf 104 -Drawing 3009 SHl.pdf 105 -Drawing 3010 SHl.pdf 106 - Drawing 3058.pdf 107 - Drawing 3070.pdf 108 - Drawing 3401.pdf 109 - Drawing 4003.pdf 110 - Drawing 4215.pdf 111 - Drawing 4259 SHl .pdf 112 - Drawing 4259 SHlA.pdf 113 -Drawing 4260 SH2A.pdf 114 - Drawing 4260 SH2B.pdf 115 -Drawing 4286.pdf 116 - Drawing 6000302 SHl .pdf 117 - Drawing 6000302 SH2.pdf 118 -Drawing 719E415BB SHl.pdf 119 - Drawing 719E479BB SHl .pdf 120 - Drawing 719E580BB SHl .pdf 121 - Drawing 729El 74BB SHl.pdf 122 - Drawing 729E211BB.pdf 123 -Drawing 729E222BB SHl.pdf 124 - Drawing 729E222BB SH2.pdf 125 -Drawing 729E222BB SH3.pdf 126 -Drawing 729E223BB SHlpdf 127 - Drawing 729E223BB SH2.pdf 128 - Drawing 729E402BB SHl .pdf 129 - Drawing 729E471BB SHl.pdf 130 - Drawing 729E471BB SH2.pdf 131-Drawing729E471BB SH3.pdf 132 - Drawing 729E471BB SH4.pdf 133 - Drawing 729E471BB SH5.pdf 134 - Drawing 729E471BB SH6.pdf 135 -Drawing 729E471BB SH7.pdf 136 -Drawing 729E517BC SHl.pdf 137 - Drawing 729E517BC SH2.pdf 138 -Drawing 729E517BC SH3.pdf 139 - Drawing 729E589BB SHl.pdf 140 - Drawing 729E589BB SH2.pdf 141 - Drawing 729E589BB SH3.pdf

NLS2017035 Page 7of14 CD-ROM NO. 2B CONTINUED I 42 - Drawing 729E7 I 9BC SHI .pdf I43 - Drawing 729E720BB.pdf I44 - Drawing 729E727BB SHI.pdf I45 -Drawing 729E727BB SH2.pdf I46 -Drawing 729E727BB SH3.pdf I47 - Drawing 729E989 SHI.pdf I48 -Drawing 730E100 SHI.pdf I49 - Drawing 730E100 SH2.pdf I50 -Drawing 730EI40BB SHI.pdf I5I - Drawing 730EI40BB SH2.pdf I52 - Drawing 730EI40BB SH3.pdf I53 - Drawing 730EI48BB SHI.pdf I54 - Drawing 730EI49BB SHI .pdf I55 - Drawing 730EI49BB SH2.pdf I56 -Drawing 730EI97BB SH6B.pdf I57 - Drawing 730E805BA SHI .pdf I58 - Drawing 730E805BA SH6.pdf I59 -Drawing 730E805BA SH7.pdf I60 -Drawing 730E923.pdf I6I - Drawing 73IE611 SHI.pdf I62 - Drawing 79IE257 SH3.pdf I63 - Drawing 79IE257 SH4.pdf I64 - Drawing 80EI I43.pdf I65 - Drawing 80El I48.pdf I66 - Drawing 9I9D690BC SH3.pdf I67 - Drawing 9I9D690BC SH5.pdf I68 -Drawing 920D225BB SHI.pdf I69 - Drawing 921D796 SHI.pdf I 70 - Drawing CNS-MS-43 .pdf I 7I - Drawing CNS-NBI-10.pdf I 72 - Drawing CPOO I SHI .pdf I 73 - Drawing DPPPG6002043800 B008247 SH5.pdf I 74 - Drawing ILE70-3 SH107B.pdf I 75 - Drawing ILE70-3 SH107C.pdf I 76 - Drawing ILE70-3 SH107E.pdf 177 - Drawing ILE70-3 SHI07F.pdf I 78 - Drawing NC29546.pdf I 79 -Drawing NC44587.pdf I 80 - Drawing SAA085 SH4.pdf I81 -Drawing SKI01670R SHI.pdf I 82 - Drawing M200 SHI .pdf

NLS2017035 Attachment I Page 8of14 CD-ROM NO. 3 USAR REVISION xxvm AND ADDITIONAL DOCUMENTS INCORPORATED BY REFERENCE PUBLIC VERSION File Name 001 - USAR List of Effective Pages.pdf 002 - USAR Table of Contents.pdf 003 - USAR List ofFigures.pdf 004 - USAR List ofTables.pdf 005 - USAR Section l .pdf 006 - USAR Section 1 Figures.pdf 007 - USAR Section II.pdf 008 - USAR Section II Figures.pdf 009 - USAR Section III.pdf 010 - USAR Section ill Figures.pdf 011 - USAR Section IV.pdf 012 - USAR Section IV Figures.pdf 013 - USAR Section V.pdf 014 - USAR Section V Figures.pdf 015 - USAR Section VI.pdf 016 - USAR Section VI Figures.pdf 017 - USAR Section VII.pdf 018 - USAR Section VII Figures.pdf 019 - USAR Section VIII.pdf 020 - USAR Section Vill Figures.pdf 021 - USAR Section IX.pdf 022 - USAR Section X.pdf 023 - USAR Section X Figures.pdf 024 - USAR Section XI.pdf 025 - USAR Section XII.pdf 026 - USAR Section XIII.pdf 027 - USAR Section XIII Figures.pdf 028 - USAR Section XIV.pdf 029 - USAR Section XIV Figures.pdf 030 - USAR Appendix A.pdf 031 - USAR Appendix B. pdf 032 - USAR Appendix C.pdf 033 - USAR Appendix C Figures.pdf 034 - USAR Appendix D.pdf 035 - USAR Appendix D(l).pdf 036 - USAR Appendix D(l) Figures.pdf 037 - USAR Appendix E. pdf 038 - USAR Appendix F.pdf 039 - USAR Appendix G.pdf 040 - USAR Appendix G Figures.pdf

NLS2017035 Page 9of14 CD-ROM NO. 3 CONTINUED 041 - USAR Appendix H.pdf 042 - USAR Appendix J.pdf 043 - USAR Appendix K.pdf 044-Tech Req Manual Section 3.pdf 045 - ISi Program Document.pdf 046 - Plant Unique Analysis Report.pdf

NLS2017035 Page 10of14 CD-ROM NO. 4A STATION DRAWINGS INCORPORATED IN THE USAR BY REFERENCE PUBLIC VERSION File Name 001 - Drawing I I 7C3346.pdf 002 - Drawing I I 7C3349.pdf 003 -Drawing 161F282BC SHl.pdf 004 ~Drawing 197R567 SHI .pdf 005 -Drawing 197R576 SHl.pdf 006 -Drawing 2001 SHl.pdf 007 -Drawing 2001 SH2.pdf 008 - Drawing 2002 SHI .pdf 009 - Drawing 2002 SH2.pdf 010 - Drawing 2004 SHl.pdf 011-Drawing2004 SH2.pdf 012 - Drawing 2004 SH3.pdf 013 - Drawing 2006 SHl.pdf 014 -Drawing 2006 SH2.pdf 015 -Drawing 2006 SH3.pdf 016 - Drawing 2006 SH4.pdf 017 - Drawing 2007.pdf 018 - Drawing 2009.pdf 019 -Drawing 2010 SHl.pdf 020 - Drawing 2010 SHIA.pdf 021-Drawing2010 SH2.pdf 022 - Drawing 2010 SH3.pdf 023 - Drawing 2010 SH4.pdf 024 - Drawing 2010 SH5.pdf 025 -Drawing 2012 SH3.pdf 026 -Drawing 2016 SHl.pdf 027 -Drawing 2016 SHIA.pdf 028 -Drawing 2016 SHIB.pdf 029 - Drawing 2016 SHIC.pdf 030 - Drawing 2017.pdf 031 - Drawing 2018.pdf 032 - Drawing 2019 SHI .pdf 033 - Drawing 2019 SH2.pdf 034 - Drawing 2020.pdf 035 - Drawing 2021.pdf 036 - Drawing 2026 SHl.pdf 037 - Drawing 2027 SHI .pdf 038 - Drawing 2027 SH2.pdf 039 - Drawing 2028.pdf 040 - Drawing 2030 SHl.pdf 041 - Drawing 2030 SH2.pdf

NLS2017035 Page 11 of 14 CD-ROM NO. 4A CONTINUED 042 - Drawing 203 I SHI .pdf 043 - Drawing 203 I SH2.pdf 044 -Drawing 203I SH3.pdf 045 - Drawing 2032 SHI .pdf 046 - Drawing 2032 SH2.pdf 047 - Drawing 2032 SH3.pdf 048 - Drawing 2032 SH4.pdf 049 - Drawing 2032 SH5.pdf 050 - Drawing 2033 SHI .pdf 05I -Drawing 2033 SH2.pdf 052 - Drawing 2033 SH3.pdf 053 - Drawing 2033 SH4.pdf 054 - Drawing 2034.pdf 055 - Drawing 2035 SHI .pdf 056 - Drawing 2035 SH2.pdf 057 - Drawing 2035 SH3.pdf 058 - Drawing 2035 SH4.pdf 059 - Drawing 2036 SHI .pdf 060 - Drawing 2037.pdf 06I - Drawing 2038 SHl.pdf 062 -Drawing 2039.pdf 063 - Drawing 2040 SHI .pdf 064 -Drawing 2040 SH2.pdf 065 - Drawing 2042 SHl.pdf 066 -Drawing 2042 SH2.pdf 067 -Drawing 2042 SH3.pdf 068 - Drawing 2043.pdf 069 - Drawing 2044.pdf 070 - Drawing 2045 SHI .pdf 07I - Drawing 2045 SH2.pdf 072 - Drawing 2049 SH3.pdf 073 - Drawing 2050 Withheld.pdf 074 -Drawing 205I Withheld.pdf 075 - Drawing 2052 Withheld.pdf 076 -Drawing 2053 Withheld.pdf 077 - Drawing 2054 Withheld.pdf 078 - Drawing 2056 Withheld.pdf 079 - Drawing 2059 Withheld.pdf 080 -Drawing 2060 Withheld.pdf 08I -Drawing 206I Withheld.pdf 082 - Drawing 2062 Withheld.pdf 083 - Drawing 2063 Withheld.pdf 084 - Drawing 2064 Withheld.pdf 085 - Drawing 2065 Withheld.pdf 086 - Drawing 2066 Withheld.pdf

NLS2017035 Page 12of14 CD-ROM NO. 4A CONTINUED 087 - Drawing 2067 Withheld.pdf 088 -Drawing 2068 Withheld.pdf 089 - Drawing 2069 Withheld.pdf 090 - Drawing 2072 Withheld.pdf 09I - Drawing 2073 Withheld.pdf 092 - Drawing 2079 SHI .pdf 093 - Drawing 2079 SH2.pdf 094 - Drawing 2080.pdf 095 - Drawing 2084.pdf 096 - Drawing 2298 Withheld.pdf 097 - Drawing 300I .pdf 098 - Drawing 3002 SHI .pdf 099 - Drawing 3003 SH2.pdf IOO -Drawing 3004 SH3.pdf

NLS2017035 Page 13of14 CD-ROM NO. 4B STATION DRAWINGS INCORPORATED IN THE USAR BY REFERENCE PUBLIC VERSION File Name IOI - Drawing 3005 SH4.pdf I02 - Drawing 3006 SH5.pdf I03 - Drawing 3007 SH6.pdf 104 - Drawing 3009 SHI .pdf 105 -Drawing 30IO SHl.pdf 106 -Drawing 3058.pdf I07 -Drawing 3070.pdf I08 - Drawing 3401.pdf I09 -Drawing 4003 Withheid.pdf I 10 - Drawing 42I5.pdf I I I - Drawing 4259 SHI .pdf I I2 - Drawing 4259 SHIA.pdf I 13 - Drawing 4260 SH2A.pdf I I4 -Drawing 4260 SH2B.pdf I I5 - Drawing 4286.pdf I I6 - Drawing 6000302 SHI.pdf I I 7 - Drawing 6000302 SH2.pdf 118 -Drawing 7I9E4I5BB SHl.pdf 119 -Drawing 7I9E479BB SHl.pdf I20 -Drawing 7I9E580BB SHl.pdf I2I - Drawing 729EI 74BB SHl.pdf I22 - Drawing 729E2I IBB.pdf I23 - Drawing 729E222BB SHl.pdf I24 - Drawing 729E222BB SH2.pdf I25 -Drawing 729E222BB SH3.pdf I26 -Drawing 729E223BB SHipdf I27 - Drawing 729E223BB SH2.pdf I28 - Drawing 729E402BB SHI .pdf I29 - Drawing 729E47IBB SHI .pdf 130 - Drawing 729E47IBB SH2.pdf 13I - Drawing 729E47IBB SH3.pdf 132 - Drawing 729E47IBB SH4.pdf 133 - Drawing 729E47IBB SH5.pdf I34 - Drawing 729E47IBB SH6.pdf 135 - Drawing 729E47IBB SH7.pdf I 36 - Drawing 729E5 I 7BC SHI .pdf 137 -Drawing 729E5I 7BC SH2,pdf 138 - Drawing 729E5I 7BC SH3.pdf I39 - Drawing 729E589BB SHI.pdf I40 - Drawing 729E589BB SH2.pdf I4I - Drawing 729E589BB SH3.pdf

NLS2017035 Page14of14 (CD-ROM NO. 4 CONTINUED) 142 - Drawing 729E719BC SHl .pdf 143 - Drawing 729E720BB.pdf 144 -Drawing 729E727BB SHl.pdf 145 -Drawing 729E727BB SH2.pdf 146 -Drawing 729E727BB SH3.pdf 147 -Drawing 729E989 SHl.pdf 148 -Drawing 730E100 SHl.pdf 149 -Drawing 730E100 SH2.pdf 150 - Drawing 730E140BB SHl.pdf 151-Drawing730E140BB SH2.pdf 152 - Drawing 730E140BB SH3.pdf 153 -Drawing 730El48BB SHl.pdf 154 -Drawing 730E149BB SHl.pdf 155 - Drawing 730E149BB SH2.pdf 156 - Drawing 730E197BB SH6B.pdf 157 -Drawing 730E805BA SHl.pdf 158 - Drawing 730E805BA SH6.pdf 159 - Drawing 730E805BA SH7.pdf 160 - Drawing 730E923.pdf 161 - Drawing 731E611 SHl.pdf 162 - Drawing 791E257 SH3.pdf 163 -Drawing 791E257 SH4.pdf 164 - Drawing 80El 143.pdf 165 - Drawing 80El 148.pdf 166 - Drawing 919D690BC SH3.pdf 167 - Drawing 919D690BC SH5.pdf 168 - Drawing 920D225BB SHl.pdf 169 - Drawing 921D796 SHl.pdf 170 - Drawing CNS-MS-43 .pdf 171 - Drawing CNS-NBI-1 O.pdf 172 -Drawing CPOOl SHl.pdf 173 - Drawing DPPPG6002043800 B008247 SH5.pdf 174-Drawing ILE70-3 SH107B.pdf 175 - Drawing ILE70-3 SH107C.pdf 176 - Drawing ILE70-3 SH107E.pdf 177 - Drawing ILE70-3 SH107F.pdf 178 - Drawing NC29546.pdf 179 -Drawing NC44587.pdf 180 -Drawing SAA085 SH4.pdf 181 -Drawing SK101670R SHl.pdf 182 - Drawing M200 SHl.pdf

NLS2017035 Page 1 of 3

SUMMARY

OF USAR DELETIONS Section of Description of Deletion Basis for Deletion Deletion Table I-3-1, Deleted Fire Hazards Analysis The FHA is no longer the Fire Protection VII-18, (FHA) as a document incorporated in Design Basis Document, as Cooper VIII-6 the Updated Safety Analysis Report Nuclear Station (CNS) has implemented (USAR) by reference. This also National Fire Protection Association resulted in the deletion of some (NFP A) 805 and the FHA has been associated FHA references and replaced by the Fire Safety Analysis Appendix R information in Sections (FSA). U. S. Nuclear Regulatory VII and VIII. Commission (NRC)-approved Frequently Asked Question (FAQ) 12-0062 provided guidance for updating the USAR for implementation of NFP A 805 and does not require the FSA to be incorporated by reference. The removal of the FHA as a document incorporated by reference without replacement is a deletion of unnecessary detail, as authorized by FAQ 12-0062 and License Amendment 248. Other FHA references and Appendix R information that were deleted are bounded by the deletion of the FHA.

III-10.3.1 Deleted statement related to stability This is excess detail as the CNS USAR licensing basis for all U.S. nuclear does not need to discuss all U.S. nuclear power plants. power plants.

V-2.3.3.2 Deleted statement that refers to The acceptability of the torus test patch future plans for removal of torus test has been documented in an Engineering patch. Evaluation and there are no restrictions as to the timeframe for removal of the test patch. Discussion of potential future removal is unnecessary detail.

VIII-2.3.3 Deleted paragraph that hypothesized This information was removed as it could an act of transmission line sabotage. be useful to a potential adversary and is unnecessary detail.

X-18 Deleted entire section titled NFP A With the implementation of License 805 Fire Safety. Amendment 248 for adoption of NFP A 805, the USAR was revised in accordance with FAQ 12-0062. With the changes made to USAR Section XIII-10 to reflect the FAQ, the detail in Section X-18 is no longer necessary and may be deleted as unnecessary detail.

NLS20I 7035 Page 2 of3 Section of Description of Deletion Basis for Deletion Deletion Figure X-4-10 Deleted stairways and elevator from This information was removed as it could floor plan in this figure. be useful to a potential adversary and is unnecessary detail that is not pertinent to the purpose of the figure.

XIII-10 Deleted various information related The Appendix R licensing basis has been to the previous Appendix R Fire superseded by implementation ofNFPA Protection Program. 805 in accordance with License Amendment 248. Section XIII-IO has been revised consistent with FAQ I2-0062. If replacement information was not included in FAQ I2-0062, it was considered excess detail.

XIII-10.4 Deleted section titled Assumptions This section detailed the history of the and Design Bases Underlying the design of the fire protection system for Fire Protection Program. the purpose of obtaining NELPIA insurance. This is deleted as excess detail that was not credited by the Atomic Energy Commission during initial licensing.

XIII-I0.5.3 Deleted section titled Fire Protection This section outlined the training Equipment Maintenance Training. program for personnel who maintain and inspect fire protection equipment in accordance with state statutes. This is deleted as excess detail that was not credited by the NRC for any fire protection licensing action.

XIII-I 0.6. I Deleted section titled Equipment This section paraphrases the Surveillance and Testing. requirements of Technical Requirements Manual Section T 3. I I, a document incorporated by reference, and is deleted as duplicate information.

XIII-I 0.6.3 Deleted section on Communications. This information is redundant to information in Section X-I6.3 and is not required by FAQ I2-0062 to be in the Fire Protection section.

XIII-I0.7.2 Deleted section titled Fire Protection This discussion is redundant to Audits. information in the Quality Assurance Policy Document, a document incorporated by reference, and is deleted as duplicate information.

NLS2017035 Page 3 of3 Section of Description of Deletion Basis for Deletion Deletion TRM Section Deleted Technical Requirements Snubber inspection and testing T 3.7.3 Manual (TRM) Section T 3.7.3, requirements are redundant to the Snubbers. inservice inspection program for snubbers required by 10 CPR '50.55a.

NLS2017035 Page 1 of6

SUMMARY

OF REGULATORY COMMITMENT CHANGES The following regulatory commitments were revised by Nebraska Public Power District (NPPD) based upon evaluation performed in accordance with Nuclear Energy Institute 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes." This summary does not include any commitment changes for which separate U. S. Nuclear Regulatory Commission (NRC) notification was provided.

Source of Commitment: Letter NLS8400021 from L. G. Kuncl (NPPD) to U.S. Nuclear Regulatory Commission dated October 1, 1984 - Response to "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability" (Generic Letter 84-15)

Letter NLS9000102 from G. A. Trevors (NPPD) to U. S. Nuclear Regulatory Commission dated March 23, 1990 - Supplemental Response to the Station Blackout (SBO) Rule, 10CFR50.63 Revision of Commitment: In the first letter, NPPD stated that a Diesel Generator reliability trend program would be established. In the second letter, NPPD indicated our intent to utilize NUMARC 87-00, Appendix D, as the

• guidance document for the Cooper Nuclear Station (CNS)

Emergency Diesel Generator (EDG) maintenance and reliability program.

An Engineering Procedure was established to trend EDG reliability based on the methodology specified by NUMARC 87-00.

Subsequently, Generic Letter 94-01 was issued which specified that licensees may now implement the provisions of the Maintenance Rule for EDGs. CNS monitors the EDGs against performance criteria for reliability and unavailability in accordance with the Maintenance Rule. CNS was established as a P 1 weather plant for the SBO rule which established the EDG target reliability of 0.95.

The Maintenance Rule Performance Criteria Basis Document for DG functions includes requirements for SBO monitoring and demonstration that the Maintenance Rule reliability performance criterion maintains the minimum target EDG reliability of 0.95.

Based on Generic Letter 94-01 and establishment of the Maintenance Rule program, the requirements for trending EDG reliability performance outside the Maintenance Rule program is no longer necessary. Therefore, the subject commitments have been withdrawn.

NLS2017035 Page 2of6 Source of Commitment: Letter CNSS870060 from G. A. Trevors (NPPD) to U.S. Nuclear Regulatory Commission dated January 27, 1987 - NPPD Response to IE Inspection Report 50-298/86-27 Revision of Commitment: This violation response stated that the procedure for refueling was revised to add a new administrative limit and a note which stated that ".... when traversing the refueling bridge between the fuel pool and the reactor cavity, the refuel mast shall be fully retracted."

This commitment was revised as follows: "When traversing the refueling bridge between the fuel pool and the reactor cavity, the refuel mast shall be one of the following: Fully retracted (NORMAL UP), or at or above safe travel height."

Recent upgrades to the refueling platform included a mast elevation indicator. Use of this indicationwill prevent damage to the mast from impact with the bellows shield. If the indicator is out of service, then the mast shall be fully retracted when traversing the refueling bridge between the fuel pool and the reactor cavity. The revised commitment continues to be responsive to the subject violation.

Source of Commitment: Letter CNSS886245 from G. A. Trevors (NPPD) to U.S. Nuclear Regulatory Commission dated August 17, 1988 - NPPD Response to Inspection Report 50-298/88-20 Revision of Commitment: This violation response stated that Surveillance Procedure 6.3 .1.1 would be amended to specify a pressure gauge with the required accuracy and readability be used for the 3 psi drywell airlock test.

This commitment was revised to refer to the "applicable surveillance procedure," as Surveillance Procedure 6.3.1.1 is no longer the appropriate procedure. Drywell airlock testing, along with test equipment requirements, is now controlled by a different procedure. Including the specific procedure number in the commitment is an unnecessary level of detail. Therefore, the commitment was revised to allow use of the appropriate surveillance procedure.

NLS2017035 Page 3of6 Source of Commitment: Letter CNSS895560 from G. R. Hom (NPPD) to U. S. Nuclear Regulatory Commission dated February 9, 1989 - Licensee Event Report 88-023, Revision 1 Revision of Commitment: In the subject report, NPPD stated that all 11 SVAC, safety-related CR120A relay coils were placed on a ten year replacement cycle.

The commitment was revised as follows: "All safety-related and normally-energized l 15VAC Model CR120A relay coils are included in the CNS Periodic Surveillance and Preventive Maintenance Program, to include coil replacement at a frequency not to exceed ten years."

The impact of the proposed change is to allow revision of relay coil Preventive Maintenance (PM) on relays that are normally de-energized. Relay coil service life is impacted by the normal state of the relay, and a normally energized relay experiences substantially higher temperatures which can impact expected service life. Normally de-energized relay service conditions in a mild environment are at room temperature, and no impact on coil service life exists. Therefore, it is not necessary for normally de-energized relays to be part of this commitment population, as there is no credible temperature aging mechanism that can affect their service life. The performance of unnecessary PMs is a resource concern, and creates the possibility that an installation or post-work testing error will result in an event or condition that could challenge a safety function.

Source of Commitment: Letter CNSS907024 from L. G. Kuncl (NPPD) to U. S. Nuclear Regulatory Commission dated January 29, 1990 - Response to Generic Letter 89-13 Revision of Commitment: This Generic Letter (GL) response stated, "The present intake structure inspection includes examination of the basin for silt, debris, and deterioration (including corrosion) and frequent monitoring of silt levels. The deterioration inspection is performed by using divers or dewatering the bay."

This commitment was revised as follows: "An examination of the safety-related E bay for silt, debris, and deterioration is performed by a diver at a :frequency in accordance with the preventive maintenance program. Frequent monitoring of silt levels is also performed."

NLS2017035 Page 4 of6 The CNS design of the Intake Structure has 5 bays which are designated as A, B, C, D, and E. The A, B, C, and D bays provide cooling water supply to the Circulating Water System pumps, which are not safety-related. The intent of GL 89-13 is to ensure safety-related Service Water equipment is maintained to acceptable levels; therefore, inspection/cleaning activities associated with bays A, B, C, and D are being segregated from this commitment. This change will limit the scope of inspections for silt, debris, and deterioration for this commitment to only E bay, which is in alignment with GL 89-13 requirements. This change also allows the frequency of inspections to be controlled in accordance with the preventive maintenance program and plant operating experience.

Source of Commitment: Letter CNSS941564 from G. R. Hom (NPPD) to U.S. Nuclear Regulatory Commission dated June 20, 1994 - NPPD Response to Inspection Report 50-298/93-202 Revision of Commitment: This violation response stated that Maintenance Procedure 7.0.2, "Preventive Maintenance," was revised to ensure appropriate review of Preventive Maintenance (PM) additions and/or changes that involve lubricants.

The appropriate review of PM additions and/or changes that involve lubricants is ensured through the PM change process review specified by the engineering procedure for the Preventive Maintenance Program. In addition, a Master Lube List is maintained that is the controlling document for lubricating equipment at CNS. This commitment was withdrawn because the process has evolved and improved over time such that a commitment for review of lubricant changes is not required. The PM change review process ensures that lubrication compatibility is properly reviewed.

Source of Commitment: Letter NLS2000020 from John H. Swailes (NPPD) to U.S. Nuclear Regulatory Commission dated November 14, 2000 - Proposed License Amendment, Service Water (SW) Backup to the Reactor Equipment Cooling (REC) Post LOCA, Response to Request for Additional Information Revision of Commitment: In response to the question "Since the alarms indicated in the Amendment Request are not essential, what Control Room indications will be used to alert the operator of the need to initiate

NLS2017035 Page 5 of6 the SW/REC backup?", CNS provided a list of the Control Room annunciators available to alert the operators of the need to initiate the SW backup cooling function. One item listed was a flow switch for "Fuel Pool Cooling Heat Exchanger low REC flow."

This flow switch has been retired-in-place and the associated Control Room annunciator has been disabled. The elimination of this switch does not affect the safety objective of the REC system to provide cooling to the Core Standby Cooling System areas. A diverse set of indications remains available to alert operators of the need to use SW backup to REC such that an active or passive failure will not challenge the supply of cooling water to the Emergency Core Cooling System areas under accident and transient conditions.

In response to the same question, CNS also identified a "flow switch

- low flow ... on each of 4 Residual Heat Removal (RHR) pumps" that provide Control Room annunciation of "RHR pump cooling water trouble." These flow switches have been removed.

Removal of these flow switches does not adversely affect the ability to monitor REC flow conditions because multiple indicators and annunciators remain available in the Control Room and will still provide sufficient warning for the need to initiate SW backup to the REC system. The indicators and annunciators that remain provide multiple temperature, pressure and flow indications to the Control Room from the REC system and Quad areas. (This second change was made in 2002, but appears to have been overlooked and not reported at that time, so it is being reported now.)

Source of Commitment: Letter NLS2002141 from Michael T. Coyle (NPPD) to U.S.

Nuclear Regulatory Commission dated November 25, 2002 - The Strategic Improvement Plan (TIP) Revision 2 Revision of Commitment: Two commitment changes were made related to the subject letter.

As part of TIP Action Plan 5.2.7.1, Improve Reinforcement of Corrective Action Program (CAP) Standards and Expectations, Action Step lh made the following commitment: "Provide CAP training to Corrective Action Review Board (CARB). This will continue reinforcement of CAP standards (i.e., problem statements, root cause, roles and responsibilities)." This commitment was revised to replace "Corrective Action Review Board (CARB)" with "applicable management review board." CNS transitioned to a new oversight board referred to as the Management Performance Review Board. Board members are required to complete training

NLS2017035 Page 6of6 that reinforces CAP standards. This change simply replaces the specific name of the site review board with more generic terminology.

As part of TIP Action Plan 5.2.7.1, Improve Reinforcement of CAP Standards and Expectations, Action Step 3a included the following commitment: "Revise CAP procedures to establish fixed timeframes for Significant Condition Report (SCR) level action items with follow-up accountability by CARB [Corrective Action Review Board]." This commitment was revised to replace "CARB" with "the applicable management review board." CNS transitioned to a new oversight board referred to as the Management Performance Review Board. One responsibility of the oversight board is to review open corrective actions from Significant Condition Reports periodically. This change simply replaces the specific name of the site review board with more generic terminology.