ML20211N626

Second Final Response to FOIA Request for Documents.Records Listed in App B Maintained in PDR Under Listed Request Number

ML20211N626
Person / Time
Issue date:	10/09/1997
From:	Racquel Powell NRC OFFICE OF ADMINISTRATION (ADM)
To:	Eubanks B AFFILIATION NOT ASSIGNED
References
FOIA-97-261 NUDOCS 9710170049
Download: ML20211N626 (2)

Text

/U#f)DCS us. NuCt:AR REGULATORY COMMIS$10N Nesc r via muut en mi g.%

FOIA -

97-261 nueONst net l',

\\e RESPONSE TO FREEDOM OF X I nN*t ( 2 n d ) I l'^a"^'

INFORMATION ACT (FOIA) REQUEST o^

OCT 0 91997 Rt OUt $ t t it Brian Eubanks PART 1.-AGENCY RECORDS HE LE ASED OR NOT LOCATED (See chw Ardhoses>

No agency records subject tr 'he request have been located.

No sdditional agency recore subject to the request have been located.

Requested records are available through another public distribution progtam. 3+e Comments section.

Arncy recards subject to the request that are identified in Apperufinles) are already available for public inspection and copying at the NRC Public Document Room. 2120 L Street, N.W., Washington DC.

Agency records sutyect to the request that are kjentified in Appendia(es)

O are being made available for pubhc inspection and copying X

st the NRC Puhhc Document Room,2120 L Strtvt N.W., Wash noton, DC,in a folder under this FOI A number.

The nonproprietary ersion of the proposal (s) that you agreed to accept in a telephoner conversation with a member of my staff is now bt,'ig made available for pubhc inspection and copying at the NRC Public Docuinent Room,2120 L Street, N.W., Washington, DC,in a folder under this F OI A number.

Apncy records subject to the request that are identified in Appendiates) may be inspected and copied at the NRC Local Public Document Room identified in the Comment: section.

Enclosed is information on how you risy obtain access to and the che gr s for copying records located at the NRC Public Document Hoom,2t 20 L $treet, N W. Washington. DC X

Agency records sutnect to the request are enclosed Records subject to the request have been referred to another F ederal agoney(ies) for review and direct response to you.

X F ees (NONE)

You will be billed by the NRC for fees totahng S You will receive a refand from the NRC in the amount of $ 35.00 in view of NRC's response to this request, no further action is being taken on appeal tetter dated

, N o.

PART ll. A-INFORMATION WITHHE LD F ROM PUBLIC DISCLOSURE Ccrttin informa* ion in the requested records is being withheld from public disclosure pursuant to the esemptions desibed in and for the reasons stated in Part II, B, C, and D. Any released portions of the documents for which only part of the record is being withheld are being made available for public insp5ction atxi copying in the NRC Pubhc Document Room 2 t20 L Street, N W., Washin, ton, DC in a toktor under this FOI A number, COMME NTS The record identified on enclosed Appendix B is the remaining record responsive to your request.

This record is enclosed.

You are not being charged fees for the processing of youl request since the minimum fee limit was not exceeded.

This completes NRC's action on your F01A.

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R3: FOIA.97 201 APPENDIX B RECORDS MAINTAINED IN THE PDR UNDER THE ABOVE REQUEST NUMBER NUMBER DATE DESCRIPTION /PAGES 1.

9/17/80 Letter to H. Parris from D. Eisenhut, subject: Sequoyah Nuclear Plant, Unit 1 Issuance of Facility Operating License, DPR 77, with enclosures, (18 pgs.).

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i F0WPA REQUEST P.O. Box 166107 Case No:

1'/' N I Little Rock, AR 72216 DateReed:

7-"~ f 7 Fourth ofJuly 1997

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b4 Director, Division of Freedom ofInformation & Publication Services

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Omce of Administration U.S. Nuclear Regulatory Coiraission Washington, D.C. 20M5 Dear Sir

'Ihis is a " Freedom ofInformation Act request",

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in accordance with pmvisions - conceming requests for public intormation on licensed nuck e erplants stated v

in the Code of Federal Regulations, Title 10, Part 9; please send to me documentation specifying the 100% core thermal power of the initial core of Unit 1 of the Sequoyah Nuclear Power Station. I wish for the 100% core thermal power rating aAer the core has been operating for sumclent time such that the faci rods become sintered in 3 zones.

My quantitative analysis titled,7hc Final Nuclear AndNeutronic Anah> sis, determined the 100% thennal power of the initial core to be 2953MW. Please send copies of the requested information to the following persons:

th Mrs. Charlene Furr, Region VI The lionorable Vic Snyder Board ofTmstees United States Department of Education 1319 Longworth liouse Omcc Building MississippilitL Omce for Civil Rights, Room 2260 Washington,DC 20515 3825 Ridgewood Road 1200 Main Street Jackson,MS 39211 Dallas,TX 75202 Thank you for your consideration of this request.

Sincerely, Brian W. Eubanks c/c:

Mr. Taylor August, Director, Omce For Civil Rights, Region VI, United States Department of FAucation Dr. Stephen 11. Balch, P:ssident, National Association of Scholars Professor Leslie E. Bauman, Chairman, Faculty Senate, Department of Physics & Astronomy, Mississippi State University Mr. Joe "The Fireballer" Black, Most Valuable Player First Game 1952 World Series, Former Brooklyn Dodger, Former Baltimore Elite Giant Dr. Michaele C. Brady, Chairman, Reactor Physics Division, American Nuclear Society Assistant Secretary Norma V. Cantu, Omce For Civil Rights, United States Department of Education President & First Lady William & liillary Clintori, President & First Lady of the United States of America Deputy Assistant Secretary Arthur L, Coleman, Omce for Civil Rights, United States Department of Justice Professor Nils J. Diaz, Commissioner, United States Nuclear Regulatory Commission Instructor Greta J. Dicus, Commissioner, United States Nuclear Regulatory Commission 1

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Professor James J. Duderstadt, Departrnent of Nuclear Engineering & Radiological Sciences, The University ofMichigan Professor O.A. Emmert, Chainnan, Department of Nuclear Engineering & Engineering Physics, University of Wisconsin at Madison

' Dr. Lyle Felsel, President, American Society for Engineering Education Mrs. Charlene Furr, Operations Director, Region VI, Omce For CMI Rights, United States Department of Education Ms. Gwendolyn Gabriel, Attomey, Rcgion VI Omce For Civil d'ghts, United States Department of Education Mr. Richard Gonzalez, Team Leader, Region VI, Omcc For Civil Rights, United States Department of Education Professor & Speaker Newt Gingrich, Speaker of the United States of America llouse of Representatives Instructor Brian K. llajek, Executive Director, American Nuclear hiciy Professor Stephen Hawking, Department of Applied Mathemaths and %corctical Physics, Univerilty of Cambridge Dr. Robert E. lienry, Chairman, nemial liydraulics Division, A merican Nuclear Society Congressman Pete llockstra, United States of America llouse of Representatives Profesor Shirley Ann Jackson, Chairman, Ucited States Nuclear Regolatory Commission Dr. Clyde Jupiter, President, Jupiter Corporation Professor William E. Kastenberg, Chairman, Depsrtment of Nuclear Engineering, University of Califomia at Berkeley Professor Mujid S. Kazimi, Chairman, Department of Nuclear Engineering, Massachusetts institute of Technology Professor Neal F. Lane, Director, National Science Foundation Conunissioner Edward McGamgan, Jr., United States Nuclear Regulatory Commission Mr. Kenneth Mines, Chief, Educational Opportunities Litigation Section, United States Department of Justice Secretary Fredrico Pena, United States Department of Energy Professor James E. Perley, President, American Association of University Professors Mr. George Peterwn, Executive Director, Accreditation Boa.rd for Engineering and Tecimology Deputy AssStant Secretary Raymond C. Picice, Omcc for Civil Rights, United States Department of Education Mrs. Isabelle Katz Pinzler, Acting Assistant Attorney General, Civil Rights Division, United States Department of Justice Mr. Robert Ramirez, Equal Opportunity Specialist, Region VI Omec for Civil Rights, United States Department of Education ne lionorable Attomey General Janet Reno, United States Department of Justice Secretary Richard Riley, United States Department of Education Professor Kenneth C. Rogers, Commissioner, United States Nuclear Regulatory Commission Secretary Rodney Stator, United States Department of Transportation Congressman Vic Snyder, United States of America 11ouse of Representatives Professor Neil E. Todreas, Department of Nuclear Engineering, Massachusetts Institute of Technology Professor James S. Tulenko, Chairman, Department of Nuclear & Radiological Engineering, University of Florida Professor Joel Weisman, Department of Mechanical, Industrial & Nuclear Engineering, University of Cincinnati -

Board of Trustees, Mississippi institutions ofliigher Leaming 2

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September 17, 1980 Docket No: 50-327 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower !!

Chattanooga, Tennessee 37401

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNIT 1 - ISSVANCE OF FACILITY OPERATING LICENSE DPR-77 The Nuclear Regulatory Comission has issued the enclosed Facility Operating License DPR-77 to the Tennessee Valley Authority for the Sequoyah Nuclear Plant, Unit 1, located in Hamilton County, Tennessee. License No. DPR-77 authorizes operation of the Sequoyah Nuclear Plant, Unit I at 100 percent power (3411 megawatts thermal) upon completion of ce5'ain related construction items.

A' Also enclosed is a copy of a related Federal Register notice which has been forwarded to the Office of the Federal Register for publication.

We are also enclosing a copy of our report " Discussion of the Environmental Effects of the Vranium Fuel Cycle", dated September 1980,

incerely, OoI re

.FE1'senhu,

rec or Division 09 Licensing Office of Nuclear Reactor Regulation

Enclosures:

1.

Facility Operating License No. DPR-77 2.

Federal Register Notice 3.

Discussion of the Environmental Effects of the Vranium Fuel Cycle cc w/ enclosures:

See next page

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l TENNESSEE VALLEY AUTHORITY l

D0ctET NO. 50-32]_

SEQUOYAH NUCLEAR PLANT. UNIT 1 FAtlllTY OPERATING LICENSE License No. DPR-77 1.

The Nuclear Regulatory Comission (the Comission) having found that:

A.

The application for licenses filed oy the Tennessee Valley Authority complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Sequoyah Nuclear Plant, Unit 1 (the facility),

has been substantially completed in conformity with Provisional Construction Permit No. CPPR-72 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.

The facility will operate in conformity with the application, as amenaed, the provisions of the Act, and the regulations of the Comission; D.

There is reawe%

ssurance: (i) that the activities authorized by this operating 1, cense can be conducted without endangering the health and safety of the public, and (ii) that such activities will be condu:ted in compliance with the regulations of the Commission set forth in 10 CFR Chapter I; E.

The Tennessee Valley Authority is technically and financially qildlified to engage in the activities authorized by this operating license in accordance with the Commission's' regulations set forth in 10 CFR Chaptsr I; F.

The Tennessee Valley Authority has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", of the Comission's regulations; G.

The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public;

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DirectoTr, Division of Freedom ofInfonnation & Publication Services Omcc of Administration 1

U.S. Nuclear Regulatory Commission i

Washington, D.C. 20555 Dear Sir 4

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'Ihis is a " Freedom ofInformation Act request".

4 In accordance with provisions - conceming requests for public information on licensed nuclear power plants statt in the Code of Federal Regulations, Title 10, Part 9; please send to me documentation specifying the 100% co:

thennal power of the initial core of Unit I of the Sequoyah Nuclear Power Station. I wish for the 100% cor i

power rating after the core has been operating for sumcient time such that the fuel rods become sinte i

My quantitative analysis titled, 7he Final Nuclear And Neutronic Anah' sit, determined the 100% the o

the initial core to be 2953MW h. Please send copies of the requ-sted information to the following persons:

t ha. Ch-Ane Furr, Region VI The Honorable Vic Snyder Board ofTmstees i

UniC 5%:s Department of Education 1319 Longworth House Omce Building MississippiIHL Ofike kr Civil Rights, Room 2260 Washington,DC 20515 3825 Ridgewood Roa Jackson,MS 39211 1200 Main Street Dallas,TX 75202

'Ihank you for your consideration of this request.

Sincerely, i

Brian W.Eubanks Mr. Taylor Augast, Director, Office For Civil Rights, Region VI, United States Department of l.

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Dr. Stephen H. Balch, President, National Association of Scholars Professor Leslie E. Bauman, Chairman, Faculty Senate, Department of Physics & Astronomy, M j

l State University l

Mr. Joe "The Fireballer" Black, Most Valuable Player - First Game 1952 World Series, Former B Dodger, Former Baltimore Elite Giant l

Dr. Michaele C. Brady, Chairman, Reactor Physics Division, American Nuclear Society Assistant Secretary Norma V. Cantu, Omcc For Civil Rights, Uni'ed States Department of Ed President & First Lady William & Hillary Clinton, President 8 First Lady of the United States o Deputy Assistant Secretary Arthur L. Coleman, Omce for Civil Rights, United States D i

i Justice Professor Nils J. Diaz, Commissioner, United States Nucl :ar Regulatory Commission Instructor Greta J. Dieus, Commissioner, United States N iclear Regulatory Commission 1

Professor James J. Duderstadt, Department of Nuclear Engineering & hadiological Sciences, The University of Michigan Professor O.A. Emmert, Chainnan, Department of Nuclear Engineering & Engineering Physics, University of Wisconsin at Madison.

Dr. Lyle Feisel, President, American Society for Engineering Education Mrs. Charlene Furr, Operations Director, Region VI, Omcc For Civil Rights, United States Department of i

l Education Ms. Gwendolyn Gabriel, Attomey, Region VI, Office For Civil Rights, United States Department of Education Mr. Richard Gonzalez, Team Leader, Region VI, Omce For Civil Rights, United States Department of Education Professor & Speaker Newt Gingrich, Speaker of the United States of America House of Representatives instructor Brian K. Hajek, Executive Director, American Nuclear Society Professor Stephen Hawking, Department of Applied Mathematics and %coretical Physics, University of Cambridge Dr. Robert E. Henry, Chairman, Hermal Hydraulics Division, American Nuclear Society Congressman Pete Hoekstra, United States of America House of Representatives Professor Shirley Ann Jackson, Chairman, United States Nuclear Regulawry Commission Dr. Clyde Jupiter, President, Jupiter Corporation Professor William E. Kastenberg, Chairman, Department of Nuclear Engineering, University of Califomia at Berkeley Professor Mujid S. Kazimi, Chairman, Department of Nuclear Engineering, Massachusetts Institute of Technology Professor Neal F. Lane, Director, National Science Foundation Commissioner Edward McGamgan, Jr., United States Nuclear Regulatory Commission Mr. Kenneth Mines, Chief, Educational Opportunities Litigation Section, United States Depar* ment of Justice Secretary Fredrico Pena, United States Department of Energy Professor James E. Perley, President, American Association of University Professors Mr. George Peterson, Executive Director, Accreditation Board for Engineering and Technology Deputy Assistant Secretary Raymond C. Pierce, Omce for Civil Rights, United States Department of Education Mrs. Isabelle Katr Pinzler, Acting Assistant Attomey General, Civil Rights Division, United States Departruent of Justice Mr. Robert Ramirez, Equal Opportunity Specialist, Region VI, Omce for Civil Rights, United States Department of Education ne Honorable Attomey General Janet Reno, United States Department of Justice Secretary Richard Riley, United States Department of Education Professor Kenneth C. Rogers, Commissioner, United States Nuclear Regulatory Commission Secretary Rodney Stator, United States Department of Transportation Congressman Vic Snyder, United States of America House of Representatives Professor Neil E. Todreas, Department of Nuclear Engineering, Massachusetts Institute of Technology Professor Jaraes S. Tulenko, Chairman, Department of Nuclear & Radiological Engineering, University of Florida Profeswr Joel Weisman, Department of Mecht.nical, Industrial & Nuclear Engineering, University of Cincinnati Board of Trustees, Mississippi institutions of Higher Leaming 2

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September 17, 1980 pacedL Docket No: 50-327 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 4

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNIT 1 - ISSUANCE OF FACILITY OPERATING LICENSE DPR-77 The Nuclear Regulatory Commission has issued the enclosed Facility Operating License DPR-77 to the Tennessee Valley Authority for the Sequoyah Nuclear Plant, Unit 1, located in Hamilton County, Tennessee. License No. DPR-77 authorizes operation of the Sequoyah Nuclear Plant, Unit I at 100 percent power (3411 megawatts thermal) upon completion of certain related construction items.

A Also enclosed is a copy of a related Federal Register notice which has been forwarded to the Office of the Federal Register for publication.

We are also enclosing a copy of our report " Discussion of the Environmental Effects of the Uranium Fuel Cycle", dated September 1980.

incerely,

w M RET .FEi'senhu rec or Division 09 Licensing Otfice of Nuclear Reactor Regulation

Enclosures:

1. Facility Operating License No. DPR-77 2. Federal Register Notice 3. Discussion of the Environmental Effects of the Uranium Fuel Cycle cc w/ enclosures: See next page \\ $0} W 'If-l}

\\. pa %9 UCENSE AUTHORITY Fil.E COPY d UNITED 5TATES 8 NUCLE AR REGULATORY COMMISSION n i WASHING TON, o. C, 20666 %...*/ 00 NOT REMOVi TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH Nt' CLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE License No. DPR-77 1. The Nuclear Regulatory Comission (the Comission) having found that: A. The application for licenses filed by the Tennessee Valley Authority complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; l B. Construction of the Sequoyah Nuclear Plant, Unit 1 (the facility), has been substantially completed in conformity with Provisional Construction Permit No. CPPR-72 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Coninission set forth in 10 CFR Chapter I; E. The Tennessee Valley Authority is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; A F. The Tennessee Valley Authority has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", of the Comission's regulations; G. The issuance of this license will not be inimical to the common i defense and security or to the health and safety of the public; ( .?nlc:da+M i 3, 7

i 2 } H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility l Operating License No. D?R-77, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 50 Appendix D, of the Commission's regulations and all applicsble requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70. 2. Pursuant to approval by the Nuclear Regulatory Commission at a meeting on September 16, 1980, the License for Fuel Loading and Low Power Testing issued on February 29, 1980, is superseded by Facility Operating License No. DPR-77 hereby issued to the Tennessee Valley Authority to read as follows: A. This license applies to the Sequoyah Nuclear Plant, Unit 1. a pressurized water nuclear reactor and associated equipment (the facility), owned by the Tennessee Valley Authority. The facility is located in Hamilton County, Tennessee, about 9.5 miles northeast of Chattanooga, and is described in TVA's Final Safety Analysis Report as supplemented and amended, and the Final Environmental Statement prepared by the Tennessee Valley Authority. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Tennessee Valley Authority: (1) Pursuant to Section 104(b) of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities", to possess, use, and operate the facility at the designated location in Hamilton County, Tennessee, in accordance with the procedures and limitations set forth in this license, (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the linitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis-Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 7n, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equiprnt calibration, and as fission detectors in amounts as required;

r l. [ (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or r special nuclear staterial without restriction to chemical or physical form, for sample analysis or instrument calibration ] or associated with radioactive apparatus or components; and i (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may , be produced by the operation of the facility. 4 i C. This license 'shall be deemed to contain and is subject to the conditions l specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, i regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated j below: e l (1) Maximum Power Level ' The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of.3411 megawatts. thermal. lq (2) Technical Soecifications it.( The Technical Specifications contained in Appendices A and B, as revised through Amendment No.J M, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. (3) Initial Test Program i The Tennessee Valley Authority shall conduct the post-fuel-loading i initial test program (set forth in Section 14 of Tennessee Valley i Authority's Final Safety Analysis Report, as amended), without i making any major modifications of this program unless modifications i have been identified and have received prior NRC approval. Major j modifications are defined as: 1 a. Elimination of any test identified in Section 14 of TVA's l Final Safety Analysis Report as amended as being essential; b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential; i } c. Performance of any test at a power level different from j there described; and .(' l

- t l _ d. Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized powerlevel). (4) Essential Raw Cooling Water (ERCW) Intake Protection (Section 2.2)* TVA shall provide analyses on the vulnerability of tht, ERCW intake structure by January 1, 1981. These analyses shall include the probability of a collision by a barge at full speed from any credible direction, including a tow proceeding in the upstream direction, and the ability of the ERCW intake to withstand such collisions, including those by barges carrying flamable cargoes (including liquid natural gas (LNG)). Operation of the new ERCW intake for Unit 2 is not permitted until this matter is resolved. (5) Onsite Meteorological Measurements Program (St.ction 2.3.3) TVA shall be required to make any de;ign modifications that the staff may deem necessary to meet the requirements of NUREG-0654, Appendix 2 and Criterion 4 of Section 2.3.3. (6) Seismic Design Margin (Section 2.5) No later than March 1,1982, TVA shall provide the results of their seismic design margin review conducted in accordance wi+,h an NRC approved seismic design margin review program for this facility. (7) Monitoring Settlement Markers (Section 2.6.3) Prior to January 1,1981, TVA shall report to the NRC on their continuing monitoring of settlement markers along the ERCW conduit for the new intake structure. The magnitude of the settlement must be determined and this matter resolved to NRC's satisfaction prior to using the new ERCW for Unit 2. (8) Low Pressure Turbine Disc Inspection (Section 3.5.1) Prior to start-up after the second refueling outage. TVA shall . reinspect the low pressure turbine discs for cracks to assure that turbine integrity will not be jeopardized. A report shall be submitted to the NRC staff 30 days after the inspection is completed.

• Referenced sections in these conditions refer to appropriate sections in the Safety Evaluation Report (NUREG-0011) and its supplements on this facility.

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.I { . (9) Steam Generator Insoection (Section 5.3.1) (a) Prior to March 1,1981 TVA shall provide to the NRC the results of its tests to determine the feasibiity of using a steam generator camera device. (b) Prior to start-up after the first refueling, TVA must install inspection ports in each steam generator if the results of the camera device inspection are not satisfactory to the NRC. (c) Prior to start-up after the first refueling, TVA will plug Row 1 of the steam generator tubes, if required by NRC. (d) By May 20, 1997, TVA shall establish a steam generator inspection program that is in accordance with the commitments listed in Enclosure 2 to the TVA letter to the Commission on this subject dated March 12, 1997, as modified by TVA letter dated March 17, 1997. (10) Water Chemistry Control Proaram (Section 5.3.2) Ot.uJ.4U4f /Jv. N This requirement has been deleted. (11) Neaative Pressure in the Auxiliary Buildina Secondary Containment Enclosure (ABSCE) (Section 6.2.3) After the final ABSCE configuration is determined, TVA must demonstate to the satisfaction of the NRC that a negative pressure of 0.25 inches of water gauge can be maintained in j the spent fuel storage area and in the ESF pump room. (12) Environmental Oualification (Section 7.2.2) (a) No later than November 1,1980, TVA shall submit i information to show compliance with the requirements of NUREG-0588, " Interim Staff Position on i Environmental Qualification of Safety-Related Elecctrical Equipment," for safety-related equipment-exposed to a harsh environment. Implementation shall l be in accordance with NUREG-0588 by June 30, 1982. 1 (b) By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document-the degree of compliance with the D0R Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further r qualified to document complete compliance by June 30, 1982. Amendment No. 222 APR 9 1997 (n. Eff 8dd

_.. _ _ m_ i.. (c) By no later than June 30,1982, all safety related electrical equipment d in the facility shall be qualified in accordance with the provisions of: 1 Division of Operating Reactors " Guidelines for Evaluating. j Environmental Qualification of Class IE Electrical Equipment in Operating Reactos" (DOR Guidelines); or, NUREG-0588, " Interim l Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to the Order for Modification of Licence DPR-77 dated November 6,1980. ( (13) IAss of Non-Class IE Instmmentation and Control Room System Bus Durine Ooeration (Section 7.10) i j Prior to exceeding five percent power, TVA must complete revisions to plant 2 emergency procedures to the satisfaction of the NRC. l' (14) Engineerine Safety Feature (ESF) Reset Controls (Section 7.11) i In conformance with IE Bulletin 80-06, TVA shall test the system to identify any further areas of concern, and TVA shall review the control schemes to j determine that they are the best in terms of equipment control and plant safety.- The results of these test and review efforts shall be provided to the NRC in accordance with the bulletin. l (15) Diesel-Generator Reliability (Section 8.3.1) i Prior to operation following the first refueling, TVA shall implement the following design and procedure modifications as outlined in Section 8.3.1 of 7 SER Supplement No. 2. These include: (a) Moisture in Air Starting System; j (b) Turbocharger Gear Drive Problem; and (c) Personnel Training. (16) Fire Protection TVA shall implement and maintain in effect all provisions of the approved fire protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011, Supplements 1,2, and 5, NUREG 1232, Volume 2, NRC l letters dated May 29 and October 6,1986, and the Safety Evaluation issued on August 12, 1997, for License Amendment No. 227, subject to the following provision: TVA may make changes to the approved fire protection program 4 without prior approval of the Commission only if those changes would 1 not adversely' affect the ability to achieve and maintain safe shutdown in (. the event of a fire, f i Amendment No. 9,227 T312 E. r

'J h 4 4 i i i[ f (17) Accident Analysis (Steam and Feedwater Line Breaks) (Section 15.2) If requested, TVA shall provide plant specific inputs toSRC for an independent audit of steam and feedwater line break analyses. s i TVA shall implement any modifications that may become necessary J as a result of these analyses or audit.

' t (18) Requirements For Modification To Or Addition Of Instrumentation c'.

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/ (a) Within 18 months after issuance of this license, instrument 4 J downscale failure alarms shall be installed for the effluent monitoring instrumentation channels for radioactive gaseous and radioactive liquid effluents. Also, appropriate modifi ' i \\ l cations to procedures and Technical Specifications 3.3.3.9 ' w ] and 3.3.3.10 shall have been conpleted.

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i (b) Within six months from issuance of this license TVA l shall submit' for NRC review the basis for the values .for each Reactor Protection System and Engineered Safety Feature instrumentation channel including: l (1) Technical Specification trip setpoint value; (2) Technical Specification allowable value (the Technical Specification trip setpoint plus the instrument drift assumed in the accident analysis); I (3) The instrument drift assumed to occur during the i interval between Technical Specification surveillance i tests; l [ (4) - The components of the cumulative instrument bias; and l (5) The minimum margin between the Technical Specification trip setpo. int, the allowable value, and the trip value . assumed in the accident analysis. t T a,u _... ~(c) At th's first outage'of sufficient duration but no later than startup gg6 following the second refueling outage TVA shall have installed. demonstrated operable, proposed appropriate Technical Specifications 'g'3 and received NRC approval for an additional level of over/undervoltage n protection acceptable to the NRC staff. The level of protection from 1 p ;(Po' the effects of power transients on safety-related equipment provided by Part I of the staff's " Degraded Grid Voltage Position," or equiva-l lent, is required. V( sT i

8-' (19) Mechanical Snthbers Within 12 months after the issuance of the license, TVA shall provide a Technical Specification listing of mechanical snubbers. In the interim, TVA will conduct a comprehensive mechanical snubber inspection program implemented by plant instructions. (20) Low Temperature Overpressure Protection (Section 5.2.?' _L At the first outage of sufficient duration but no later than 85 0 startup following the second refueling outage. TVA shall install 5/a 3 i an overpressure mitigation system which meets NRC requirements.,__/=h37&k (21) Control Rod Guide Thimble (Section 4.2) Prior to startup after first refueling, TVA shall submit the details of the inspection program for control rod guide thimble tube wall wear for NRC approval. (22) TMI Action Plan Full Power Conditions Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated: A. Safety Engineering Group (Section 22.2.I.B.1.2) Prior to exceeding five percent power, TVA is required to have an onsite Safety Engineering Group. NRC will verify the adequacy of the Safety Engineering Group and its independence. B. Short-Term Accidert Analysis and Procedure Revision (Section 22.2.I.C.1) d Within thirty effective full-power days, TVA shall revise Emergency Operating Procedures and brief the operators on the revision. C. Control Room Design (Section 22.2.1.D.1) TVA shall consider the benefits of installing data recording g_f., and logging equipment in the control room to correct the l deficiencies associated with the trending of important N parameters on strip chart recorders used in the control room j g yj_ gg as part of the Detailed Control Room Design Review. Impl emen-tation shall be carried out in accordar.ce with SECY 82-1113.

e 9 3,C/A))D. Hydrogen control Measures (section 22.2.11.B.7) 4/42 (1) Four additiont.1 igniter units shall be installed in the con-A tainment upper containment compartment in locations accept-abla to the NRC staff prior to startup following the second

1. gT refueling outage.

(2) Additional tests shall be perfonned on the Tayco igniter

• **I to demonstrate that the igniters will initiate combustion in a spray environment such as that expected in the upper

-compartment of the ice condenser containment. (a) TVA shall amend its research program on hydrogen control measures to include, but not be limited to, the following items: 1) Improved calculational methods for containc.ent tempera-ture and ice condenser response to hydro 5en cerbustion. l

2) Research to address the potential for local. detonation.

'o 3) Confirmatory tests on selected equipment expcsed to g hydrogen burns. g

4) New calculations to predict differences between expected equipment temperature environments and containment tem-jg.g peratures.

5) Evaluate and resolve any anomalous results occurring during the course of its ongoing test program.

(b) A schedule for confirmatory tests shall be provided by TVA consistent with the requirement to meet Section (22)D.(2) of the license. 9 \\ ( ( s

W { lydrogen Control Measures (Section 22.2.ll.B.7) y# Dltr(ng the interim period of operation. TVA shall cont,nue a V reseaKprogram on hydrogen control measures and th(effects ,f'y of hydroge burns on safety functions and shall su6mit to the NRC 1 quarterly re s on'th4t research program. k@ (a) 'TVA shall ame its research programjm hydrogen control measures to inc de, but not lin.it (to, the following items: I (1) Improved cal lational thods for containment temperature J and ice condens res nse to hydrogen combustion and i#j,ld local detonation. a f M F bj (ii) Confirmatory tes s on elected equipment exposed to j gC hydrogen bur I d#q (iii) New calculations to predict ifferences between expected pr equipmpnt temperature environn nts and containment te eratures. (iv) faluate and resolve any anomalous suits from the ongoing test program. (b he results of these investigations will be prov ded to the staff for review in May 1981. A schedule for confiq.iatory tests beyond this date will be provided consistent with the require-s / ment to meet the January 31, 1982 deadline,Section(22]D(2)of the license. E. Auxiliary Feedwater (Section 22.2.11.E.1.1) Prior to exceeding five percent power, auxiliary feedwater pump endurance tests will be completed and a report will be submitted to NRC within 30 days after all tests are canpleted. gg F. Radiation Moniters (Section 22.2 II.E.4.2) P" #- ANPT 6 TVA will instail Radiation Monitors for isolation of fluid lines carrying potential radioactivity cutside of containtnent at the earliesi practical date consistent with scheduled or forced plant outages tut V27-81 prior to operation following the first rsfueling. G. Emergency Preparedness Plan (Section 22.2.III.A.1.1 And Appendix E) (a) TVA shall maintain in effect an emergency plan that meets

• }

the regulatory requirement of 10 CFR Part 50, Appendix E, and the operator Planning Objectives of NUREG-0654, Criteria for Preparation and Evaluation of Radiological Preparedness >f / in Support of Nuclear Power Plants," Jan'uary 1980. / (b) No later than 90 days from the date of issuance of this / license, TVA shall report to the NRC the status of any items t 3 related to emergency preparedness identified by FEMA or the NRC as requiring further action.

10 - (23) TMI Action Plan Dated Conditions Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated: A. Shift Technical Advisor (Section 22.3. I. A.1.1) TVA shall continue to provide an on-shift technical advisor to the shift operations supervisor. l All STAS shall be fully trained no later than by January 1, 1981. STAS shall complete eight weeks of mathematics, physics, thermodynamics, fluid flow, heat transfer, 4 instrumentation and control, chemistry, materials and structural analysis. Following this, STAS shall receive two weeks of design review and five weeks of systems dynamic a behavior including transient analysis and techniques for transient identification. The training program for engineers designated as STAS shall consist of three portions: academic training in thermodynamics, fluid flow, heat transfer and reactor theory; specific instruction in plant systems and Technical Specifications; and finally, simulator training, i The training shall be taught at the college level and be equivalent *.o about 60 semester hours. Items for completion by January 1, 1981: B. Plant Shieldina (Section 22.3. II.B.2) TVA shall complete modification to assuie adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core. C. Auxiliary Feedwater Initiation and Indication (Section 22.3. II.E.1.2) (a) TVA shall upgrade, as necessary, automatic initiation of the auxiliary feedwater system to safety-grade quality. (b) TVA shall upgrade, as necessary, the indication of auxiliary feedwater flow to each steam generator to safety grade quality. D. Additional Accident Monitorino Instrumentation (Section 22.3. II.F.1) ~;(- (1) TVA shall install interim noble gas monitors at the first outage of sufficient duration. Amendment No. 10, 178 O l 694

77 ~ i -//- f,c ht)D. Additional Accident Monitorine Instrumentation (Section 22.3,11.F.Tj" w (1) TVA shall insta'll' interim noble gas munitors at the first outtge' of suf ficient duration. f-- 1 I (2) At the first outage of sufficient duration but no later than q startup following the second refueling outage. TVA shall install the follovving qualified monitoring instrumentation: (a) Integrated monitoring assembly which will accomplish pg, particulate, iodine and noble gas monitoring. e l b Containment high range radiation monitor. /g c Containment pressure monitor. g.y,g d Containment water level monitor. e Containment hydrogen monitor. ~ 4..c(ii.lE. Rea'eto'r Cool y Vents (Section 22.3. !!.B.1) [, ~. ' ~ v ::~h '.71' r... p p.a 'L At the first outage of sufficient duration but no later than I' startup following the second refueling. outage. TVA shall install reactor. coolant system and reactor vessel head highpoint vents that are remotely operable from the control ro,om. -t ._.-.w.--.. Q.c 623)F. Post Accident Sampling (Section 22.3, II.B.3) ~- Amo+. TVA is authorired to operate the installed Post Accident Samp1-g ~ ing System as described in their letters dated November 23 and December 21, 1983 January 9 and 10, and March 23, 1984 The

• g _ g.

/*~. system shall be operable no later than startup following the p l, second refueling outage. f 2.C.(A G. Oclo tLd-pr Amd.t.10 mls ty; ,J.c(opi. Instruments of Inadequate Core Cooling (Section 22.3, II.F.2) (1) By January 1,1982 TVA shall install a backup indication for Arr$4 incore thermocouples. This display shall be in the control

• /o room and cover the.terperature range of 200 F - 2000 F.

/JM/-2/ ~ ~ ~ (2). At the first outage of suffichnt duration bu't no later than startup following the second refueling outage, TVA shall install Amdy, reactor vessel water level instrumentation which meets NRC Mea 3 requirements. g, c (a$f. Up :rade Emercency Support Facilities '(Section 22.3, ::. A.*. 2) /097-85 (1) At the first outage of sufficient duration but no latt.r than startup following the second refueling outage, TVA shall update the Technical Support Facilities to meet NRC requirements. i f , 's k (2) TVA shall maintain interim emergency support facilities (Tech-4*d#' nical Support Center, Operations Support Center and the Emergency M Ooerations Facility) until the final facilities are c.orrlete. /2M G

~. _ _. - t (2) TVA shal'1 maintain interim emergency support facilities (Technical Support Center, operations support Center and the Emergency operations Facility) until the final facilities are complete. hDff}(L M Q.M Relief and Safetv Valve Test Reauirements (Section 22.2. fhTd3..-4 to (ht%( II.D.11 e ID ~ 3I' h TVA ehall cer. form to the resulte of the EPRI test program. TVA sha)' provjde documentation for qualifying (a) reactor coo) Lit system relief and safety valves, (b) piping and supports, and (c) block valves in accordance with the 3 review schedule given in SECY 81-491 as approved by the commission. l (24) Como11ance with Raoulatory cuide 1.97 TVA shall implement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following An hccident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage. (25) Mixed Core DNBR Penalty TVA will obtain NRC approval prior to 9e r tup for any cycle's core that involves a reduction in the c; 4-ture from nucleate boiling ratio initial transition core pu1>.o y below that value stated in TVA's submittal on Framatome fuel conversion dated April 6, 1997. lAE D. Exemptions from certain requirements of Appendices G and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluat' ion Report, Supplements No. 1. These exemptions are authorized by law and will not endanger life or property or the common defence and security and are otherwise in the public interest. The exemptions are, therefore, hereby granted. The granting of these i exemptions are authorized with the issuance of the License for Fuel Loading and Low Power Testing, dated February 29, 1980. The facility will operate, to the extent authorized herein, Act, and the R77 regulations of the Commission. Additional exemptions are listed in attachment 1. 2 E. Physical Protection The licensea shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguarde contingency plans including amendments ma'de pursuant to provisions of the Miscellaneous Amendrnents and Search Requirements revision to 10 CFR 73.55 (51 FR 27817 and 27822) anc to the authority of 10 CFR 50.90 and 10'CFR 50.54(p). The Safeguards contingency Plan is incorporated into the Physical Security Plan. The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Sequoyah Physical Security Plan," with revisions submitted through November 23, 1987; and "Sequoyah Security Personnel Training and Qualification Plan," with revisions submitted through April 16, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein., Unit 1 Amendment No. 10, 53, 73, 193, 200, 213, 223 A#3 2 ? C 7 i Amendment No. 73 June 24, 1988

/ 2. w - (. F. This license is subject to the following auditionil condition for the j protection of the environment: Before engaging in additional construction or operational activities 'which may ryult in an environmental impact that was not evaluated i by the Conmission. Tennessee Valley Authority will prepare and record ,. / 4 + 1 4 i ~ t !( 3 i e T t 4 I 1 l '~

. esps an environmental evaluation of such activity. When the evaluation l Indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater thari that evaluated in the Final Environmental Statemant prepared by the Tennessee Valley Authority and the Environmental Impact Appraisal prepared by the Comission in May 1979, the Tennessee Valley Authority shall provide a written evaluation of such activities and obtain pricr approval from the Director, Office of Nuclear Reactor Regulatiert. G. If TVA plans to remove or to make significant changes in the normal operation of eouipment that controls the amount of radioactivity in effluents from the Sequoyah Nuclear Plant, the Commission shall be notified in writing regardicss of whether the change affects the amount of radioactivity in the effluents. H. TVA shall report any violations of the requirements contained in Sections 2.C(3) through 2.C.(24), 2 E, 2.F and 2.G of this license within 24 hours by telephone and confirmed by telegram, mailgram, or facsimile transmission t.o the Director of the Regional Office, or his designate, no later than the first working day following the violation with a written followup report within 14 days. I. TVA shall imediately notify the Commission of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission. J. TVA shall h6ve and maintain financial protection of such type and in such amounts as the Comission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims. K. This amended license is effective as of the date of issuance and shall MD3 expire September 17, 2020. W9-98 FOR THE NUCLEAP REGULATORY COPHISSION / rkt h Y Harold R. Denton, Director Office of Nuclear Reactor Regulation

Attachment:

Appendices A and B Technical Specifications t' ate of Issuance: September 17, 1980 (_

(.lCENSE AUTHORITY FILE 00PY, MFREW UNITED STATES NUCLEAR REGULATORY COMMISSION g g g DOCKET NO. 50-327 gm TENNESSEE VALLEY AUTHORITY Afg 9. /1-yo, NOTICE OF ISSUANCE OF FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Facility Operating License No' DPP-77, to Tennessee Valley Authority (licensee) which authorizes operation of the Sequoyah Nuclear Plant, Unit 1 (the facility) at reactor core power levels not in excess.of 3411 megawatts thermal (100 percent power) in accordance with the provisions of the license and the Technical Specifications. Prior to power operation at power levels exceeding 5 percent, certain related construction items must be completed. The Sequoyah Nuclear Plant, Unit 1 is a pressurized water nuclear reactor located lg at the licensee's site in Hamilton County, Tennessee, about 9.5 miles northeast of Chattanooga. i The application for the license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. The Comission has made appropriate findings as required by the Act and the Comission's regulations in 10 CFR Chapter I, which are set forth in the license. Prior public notice of the overall action involving the proposed issuance of an operating license was published in the FEDERAL REGISTER on March 25,1974 (39 FR 11131). The notice of issuance of license of February 29, 1980 for fuel loading and low power testing was published in the FEDERAL REGISTER on March 10,1980 (45 FR 15349). The Commission has determined that the issuance of this license will not result in any environmental impacts other than those evaluated in the Final Environmental Statement since the activity authorized by the license is encompassed by the overall r action evaluated in the Final Environmental Statement. Dp f

. l For further details with respect to this action, see (1) License for Fuel Load and Low Power Testing dated February 29, 1980 andamendmentsthereto;(2) Facility Operating i.icense No. DPR-77, complete with Technical Specifications, and (3) the ~ reports of the Advisory Committee on Reactor Safeguards dated December 11,1979, July 15, 1980, and September 8,1980;(4) Comission's Safety Evaluation Report (RUREG-0011) dated Marct.1979, Supplement No. I dated February 1980, Supplement No. 2 dated August,1930, and Supplement 3 dated September 1980; (5) the Final Safety Analysis Report and amendments thereto; (6) the Final Environmental Statement prepared i by Tennessee Valley Authority in 1 Comission's Environmental Impact Appraisal dated May 1979; (8) NRC Flood Plain Review of Sequoyah Nuclear Plant Site dated Jul,o 18,1980; and (9) Discussion of the Environmental Effects of the Uranium Fuel Cycle dated September 1980. These items are available for public inspection at the Commission's Public Document Foam,1717 H ftreet, N. W., Washington, D. C., and the Chattanooga s Hamilton County Bicentennial Library,1001 Broad Street, Chattanooga, Tennessee 37402. A copy of Facility Operating License No. DPR-77 may be obtained upon request address'.' to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: 4 4 Director, Division of Lic ising. A copy of item (4) may be purchased at current rates from the National Technical Information Service, Department of Comerce, 5285 Port Royal Road, Springfield, Virginia 22161, and through the NRC GP0 sales program i by writing to U.S. Nuclear Regulatory Comission, Attention: Sales Manager, Washington, D. C. 20555. GPO deposit account holders can call 301-492-9530. Dated at Bethesda, Maryland, this 17th day of September,1980. FOR THE NUCLEAR REGULATORY COPfi!SSION W !( A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing}}