ML20009A680
| ML20009A680 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/17/1981 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Bradford P, Gilinsky V, Hendrie J NRC COMMISSION (OCM) |
| Shared Package | |
| ML20009A670 | List: |
| References | |
| REF-10CFR9.7 NUDOCS 8107130467 | |
| Download: ML20009A680 (36) | |
Text
a
'o UNITED STATES NUCLEAR REGULATORY COMMISSION o
3 E
WASHWGTON. D. C. 20555 s,...l. /
a, Docket No. 50-328 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNIT 2 - ISSUANCE OF FACILITY OPERATING LICENSE The Nuclear Regulatory Connission has issued the enclosed Facility Operating License No. DPR-79 to the Tennessee Valley Authority for the Sequoyah Nuclear Plant, Udit 2, located in Hamilton County, Tennessee. License No. DPR-79 authorizes operation of the Sequoyah Nuclear Plant, Unit 2, at 100 percent power (3411 megawatts thermal) upon completion of certain related construction items.
Also enclosed is a copy of Supplement No. 5 to the Safety Evaluation Report, together with a related Federal Register notice which has been forwarded to the Office of the Federal Register for publication.
Two signed originals of Amendment No. 7 to Indemnity Agreement No. B-82 which covers the activities authorized under License No. DPR-79 are also enclosed.
Please sign and return one copy to this office.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
1.
Facility Operating License No. DPR-79 2.
Federal Register Notice 3.
SER Supplement 5 4.
Amendment 7 to Indemnity Agreement B-82 cc w/ enclosures:
See next page i
8107130467 810617 i
Tennessee Valley Authority ccs:
Herbert S. Sanger, Jr. Esq.
Mr. Bruce Blanchard General Counsel Enytronmental Projects Review Tennessee Valley Authority Department of the Interior 400 Commerce Avenue Room 4256 E 118 33 18th and C Street, N. W.
Knoxville, Tennessee 37902 Washington, D, C. 20240 Mr. E. G. Beasley Defense Mapping Agency Tennessee Valley Authority Aerosrace Center Wl0Cl31 C St. Louis Air Force Station 400 Comerce Avenue Missouri 63118 Knoxville, Tennessee 37902 Federal Energy Regulatory Comission Mr. Michael Harding 825 North Capital Street, N, E, Westinghouse Electric Corporation Washington, D. C. 20426 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chairman Tennessee Public Service Comission Mr. David Lambert Cl-102 Cordell Hull Building Tennessee Valley Authorit/
Nashville, Tennessee 37219 400 {hestnut Street Tower II Chattanooga, Tennessee 37401 Mr. J. F. Cox Tennessee Valley Authority Director 400 Co=erce Avenue, W10C131C Of fice of Urban & Federal affairs Knoxville, Tennessee 37902 108 9arkway Towers 404 James Robertson Way ResidentInspector/SequoyahNPS Nashville, Tennessee 37219 c/o U. S. Nuclear Regulatory Commission P. O. Box 699 The Honorable Don Moore, Jr.
Hixson, Tennessee 37343 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37201 i
U.S. Environmental Protection Agency l
ATTN: EIS Coordinatur f
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Region IV Office l
345 Courtland St., N. E.
l Atlanta, Georgia 30308 Attorney General Supreme Court 'ouilding Nashville,",ennessee 37219 i
l U.S. Environmental Protection Agency Attn: Ms. F. Munter l
Office of Federal Activities Room W-535, Waterside Mall l
401.M Street, S. W.
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Washington, D. C. 20460 l
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
aj WASH:NGTON, D. C. 20555
'+9.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) having found that:
A.
The applicaticn 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 Commission's regulations set forth in 10 CFR Chapter I, arid all required notifications to other agencies or bodies have been culy made; B.
~ Construction of the Sequoyah Nuclear Plant, Unit ~2 (the facility),
has been substantially completed in conformity with Provisional Construction Permit No. CPPR-73 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 Comission; D.
There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted wi.thout endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the C' mmission 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 Commission's regulations, set forth in 10 CFR Chapter I; F.
The Tennessee Valley Authority has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", cf the Cermission's regulations; i
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;
., 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 Operating License No. DPR-79, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 50, Appendix D*, of the Comission's regulations and all applicable 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 June 17, 1981, Facility Operating License No. DPR-79 is hereby issued to the Tennessee Valley Authority to read as follows:
A.
This license applies to the Sequoyah Nuclear Plant, Unit 2, 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 CFD oart 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 l
l 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 limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; l
(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 l
monitoring equipment calibration, and as fission detectors in amounts as required;
- See 10 CFR S 51.56
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 special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (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.
C.
This license shall be deemed to contain and is subject to the conditions 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, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1 ) Maximuir Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in axcess of 3411 megawatts thermal.. Fuel loading and operation of the facility is subject to compliance with construction items listed in.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B attached hereto are hereby incorporated in this license. The Tennessee Valley Authority shall operate the facility in accordance with the Technical Specifications.
(3)
Initial Test Program l
The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
l 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; c.
Performance of any test at a power level different from that described in the program; and i
i l
c
., d.
Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized power level).
(4) Monitoring Settlement Markers (Section 2.6.3)
TVA shall continue to monitor the settlement markers along the ERCW conduit for the new ERCW intake structure for a period not less than three years from the date of this license. Any L
settlement greater than 0.5 inches that occurs during this period will be evaluated by TVA and a report on this matter will be submitted to the NRC.
(5) Design of Seismic Category Structures (Section 3.8) 4 Prior to startup following the first refueling, or as directed by the Commission, TVA shall evaluate all seismic Category I masonry walls to final staff criteria and implement required modifications that are indicated by that evaluation.
(6) Tornado Missiles (Section 3.5)
Prior to startup after the first refueling, TVA shall reconfirm to the satisfaction of the NRC that adequate tcrnado protection is provided for the 480 Y transformer ventilation systems.
(7) Low Temperature Overpressure Protection (Section 5.2.2)
Prior to startup after the first refueling, TVA shall install an overpressure mitigation system which meets NRC requirements.
(8) Steam Generator Inspection (Section 5.3.1)
Prior to start-up after the first refueling, TVA must install inspection ports in each steam generator or have an acceptable alternative for inspection.
(9) Negative Pressure in the Auxiliary Building Secondary Containment Enclosure (ABSCE) (Section 6.2.3)
After the final ABSCE configuration is established and prior to exceeding 5 percent power level, TVA must demonstrate to the satisfaction of the NRC that a negative pressure of 0.25 inches of water gauge can
- be maintained in the spent fuel storage area and in the ESF pump room.
t (10) Containment Isolation Systems (Section 6.2.4)
Prior to startup after the first refueling, TVA shall modify to the satisfaction of the NRC the one-inch chemical feed lines to the l
main and auxiliary feedwater lines for compliance with GDC 57.
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1 l
(11) Environmental Qualification (Section 7.2.2) l (a) No later than June 30, 1982, TVA shall be in compliance with l
the requirements of NUREG-0588, " Interim Staff Position on l
Environmental Qualification of Safety-Related Electrical l
Equipment," for safety-related equipment exposed to a harsh environment.
(
(b) Complete and auditable records must be available and maintained at a central location which describe the environmental qualifica-tion method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the l
D0R Guidelines or NUREG-0588. Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30,1982.
(c) Within 90 days of receipt of the equipment qualification sdety evaluation, the licensee shall either (i) provide missing j
documentation identified in Sections 3 and 4 of the equipment l
qualification safety evaluation which will demonstrate compliance i
of the applicable equipment with NUREG-05A8, or (ii) commit to l
corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.
l (12) Requirements For Modification To Or Addition Of Instrumentation j
And Controls (7.3.2)
L (a) Prior to startup after first refueli' rig, TVA shall have installed instrument downscale failure alanns for the effluent monitoring instrumentation channels for radioactive gaseous and radioactive liquid effluents. Also, appropriate modifications to procedur s and Technical Specifications 3.3.3.9 and 3.3.3.10 shall have been completed.
(b) Prior to startup after the first refueling, TVA shall have installed, demonstrated operable, proposed appropriate Technical Specifications, and received NRC approval for an additional level of over/undervoltage protection acceptable to the NRC staff. The level of protection from the effects of power transients on safety-related equipment provided by Part I of the staff's " Degraded Grid Voltage Position",
or equivalent, is required.
(13) Diesel Generator Reliability (Section 8.3.1)
Prior to operation following the first refueling, TVA shall implement the following design and procedure modifications as
)
outlined in Section 8.3.1 of SER Supplement No. 2.
These include: (a) Moisture in Air ! 'eting System; (b) Turbocharger Gear Drive Problem; and (c) Personn;, Training.
1
6-(14) Fire Protection System (Section 9.5) a.
TVA shall maintain in effect and fully implement all provisions of the approved fire protection plan and the NRC staff's Fire Protection Review in Supplements 1, 2 and 5 to the Sequoyah Safety Evaluation Report. By July 1981, TVA shall implement the following three items which deal with the ERCW supply: (a) enclose the necessary exposed conduit with a 1-1/2-hour fire barrier; (b) reroute train B ERCW pump and transformer power cables to obtain a minimum 20-foot separation from train A; and (c) enclose the ERCW junction box with a 1-1/2-hour fire barrier..
b.
Afte* initial criticality of Unit 2 and prior to the completion of ites (a) above, TVA shall provide:
- 1) a continuous fire watch in the area of the ERCW junction box on elevation 690.0 of the auxiliary building.
- 2) c roving fire watch in the area of conduits which exit the top of the junction box, pass through floor elevation 714.0, and terminate on floor elevation 734.0.
c.
TVA shall replace the control room ceiling panels with panels acceptable to NRC by September 1,1981.
d.
By October 1,1981, TVA shall submit a report that identifies and justifies differences between existing or proposed fire protection features and these features specified in Sections III.G, III.J, III.L, and III.0 of Appendix R to 10 CFR Part 50.
TVA shall implement any fire protect. ion features found appropriate l
by the NRC on a schedule consistent with that required for other operating reactors.
(15) Mechanical and Hydraulic Snubbers Prior to exceeding 5 percent power, TVA shall provide a listing of mechanical snubbers on safety-related systems. Functional testing of snubbers shall be carried out in sccordance with the Technical Specifications.
(16) Compliance with Regulatory Guide 1.97 By June 30, 1981, TVA shall submit a proposal, including an implementation schedule, for compliance with R.G.1.97.
(17) NUREG-0737 Conditions (Section 22.2)
Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated:
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- a.
Shift Technical Advisor (Section 22.2, I.A.1.1)
TVA shall provide a fully-trained on-shift technical advisor to the shift supervisor, b.
Independent Safety Engineering Group (Section 22.2, I.B.1.2)
TVA shall have an onsite Independent Safety Engineering Group.
c.
Procedures for Verifying Correct Perfomance of Operating Activities (Section 22.2, I.C.6)
Procedures shall be available to verify the adequacy of the operating activities.
d.
Control Room Design (Section 22.2, I.D.1)
Prior to start-up after first refueling of Unit 1, TVA shall complete the detailed Control Room Design Review. As part of this review, i
TVA shall consider benefits of installing data recording and logging equipment in the control room to ccrrect the deficiencies associated l
with the trending of important parameters on strip chart recorders used in the control raom. All corrective actions specified for Unit 1, shall be made on Unit 2 prior to n:eeding 5 percent power level.
i l
e.
Training During Low-Power Testing (Section 22.2, I.G.1)
Licensed operators shall complete simulator training for natural circulation conditions prior to exeeding 5 percent power level.
One experienced operator trained on UMt 1 low power testing for natural circulation operation shall be assigned to each shift prior to exceeding 5 percent power level. Requirement remains in effect until TVA submits a report and NRC agrees with findings that an acceptable level of training and experience on Unit 2 has been attained.
f.
Reactor Coolant System Vents (Section 22.2, II..B.1) l By July 1,1982, TVA shall install reactor coolant system and reactor vessel head highpoint vents that are remotely operable from the control room.
g.
Post Accident Sampling (Section 22.2, II.B.3)
By January 1,1982, TVA shall complete corrective actions needed to provide the capability to promptly obtain and perfom radioisotopic and chemical analyses of reactor coolant and containment atmosphere samples under degraded core conditions without excessiv i exposure.
5
- h.
Hydrogen Control Measures (Section 22.2, II.B.7)
(1) For operation of the facility beyond January 31,1982, the Comission must confirm that an adequate hydrogen control system for the plant is installed and will perfom its intended function ht a manner that provides adequate safety margins.
l (2) During the interim period of operation, TVA shall continue a l
research program on hydrogen control measures and the effects of hydrogen burns on safety functions and shall submit to the NRC quarterly reports on that research program.
(a) TVA shall amend its research program on hydrogen control measures to include, but not limited to, the following i
items:
i
- 1) Improved calculational methods for containment temperature and ice condenser response to hydrogen combustion.
- 2) Research to address the potential for local detonation.
l
- 3) Confirmatory tests on selected equipment exposed to I
hydrogen burns.
l
- 4) New calculations to predict differences between expected equipment temperature environments and containment temperatures.
- 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 the January 31, 1982 deadline, Section (17)h.(1) of the license.
l i.
Relief and Safety Valve Test Requirements (Section 22.2, II.D.1)
TVA shall confom to the results of the EPRI test program.
Documentation for qualifying the reactor coolant system relief and safety valves under expected operating conditions for design basis transient accidents is to be completed by October 1981. Documentation on piping and supports is required by January 1982. Block valves are to be qualified by July 1982.
I I
=
-. - ~. - - - -
. l
- j. Auxiliary Feedwater (Section 22.2, II.E.1.1) l Prior to exceeding five percent power, auxiliary feedwater pump l
endurance tests will be completed and a report will be submitted to NRC within 30 days after all tests are completed.
k.
Containment Isolation Dependability (Section 22.2, II.E.4.2)
TVA shall limit the purge valve openings to less than or equal to 50 degrees.
1.
Additional Accident Monitoring Instrumentation (Section 22.2, II.F.1)
By January 1,1982, TVA shall install continucus indication in the control room of the following parameters:
(1) Containment radiation monitors.
l (2) Noble gas effluent from each potential release point.
m.
Instruments for Inadequate Core Cooling (Section 22.2, II.F.2)_
(1) TVA shall provide a reactor vessel water level instrumentation system by January 1,1982.
l (2) TVA shall submit a proposal for upgrading the incore thermocouple system in Juns 1981. TVA shall upgrade the incore thermocouple system by January 1,198f.
n.
Voiding in Reactor Coolant System (Section 22.2, II.K.2.17) 1YA is participating in the Westinghouse owners group effort on this item and shall conform to the results of this effort. The analysis will be submitted by January 1,1982.
Sequential Auxiliary Feedwater Flow Analysis (Section 22.2. II.K.2.19) o.
l TVA is participating in the Westinghouse owners group effort on this item and shall conform to the results of this effort.
The analysis will be submitted by July 1,1982.
p.
Calculations for Small-Break LOCAs (Section 22.2, II.K.3.30 and II.K.3.31 )
TVA is participating in the Westinghouse owners group effort for this item and shall confonn to the results of this effort.
The analysis for model justification will be submitted by January 1, 1982.
q.
Upgrade Emergency Preparedness (Section 22.2, III.A.1.1)
TVA is required to have a prompt notification system installed and operational by July 1,1981.
Upgrade Emergency Support Facilities (Section 22.2, III.A.1.2) r.
(1) TVA shall have in operation the upgraded emergency support facilities by October 1,1982 consistent with the guidance of NUREG-0696 and in accordance with the provisions of NRC letter to TVA dated March 19, 1981.
(2) TVA shall maintain interim emergency support facilities (Technical Support Center, Operations Support Center and the i
Emergency Operations Facility) until the final facilities are complete.
l s.
l.ong-Tenn Emergency Preparedness (Section 22.2, III. A.2)
Additional implementation dates for the meteorological program are:
l l
(1) Prior to exceeding 5 percent power level of Unit 2, TVA will comit to providing for direct telephone access to the individual responsible for making off-site dose projections in the event of a radiological emergency.
(2) Functional description of upgraded capabilities shall be provided by January 1,1982.
Installation of hardware and sof tware shall be completed by July 1,1982. Full operational capability is required by October 1,1982.
t.
Primary Coolant Outside Containment (Section 22.2, III.D.1.1)
Prior to exceeding 5 percent power level, TVA is required l
to submit the leak test results of Unit 2.
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 l
Evaluation Report, Supplements No.1 and No. 5.
These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. Tb facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act,
]
and the regulatic,ris of the Commission.
I
. A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 5, Section 6.2.4.
This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. The exemption, therefore, l
1s hereby granted and shall remain in effect through the first refueling outage as discussed in Section 6.2.4 of Supplement 5 to the Safety Evaluation Report.
The granting of the exaption is authorized with the issuance of the Facility Operating License. The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
E.
The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, guard training and qualification plan, and safeguards contingency plan, including amendments made pursuant to the authority of 10 CFR 550.54(p). The approved plans consist of 10 CFR 52.790(d) information collectively entitled:
" Physical Security Plan for the Sequoyah Nuclear Plant", dated August 25, 1978, as revised on April 2,1979, June 29, 1979, September 19, 1979, and December 16,1980; "Sequoyah Nuclear Plant Security Personnel Training and Qualifications Plan" dated August 17, 1979, as revised January 24,1980, May 21,1980, October 1,1980, March 9,1981, and as amended by subsequent approved revisions; and the "Sequoyah Nu:: lear Plant Safeguards Contingency Plan", dated March 1,1979, as revised September 1, 1979, April 15,1980, December 21,1980, March 30,1981, and as amended by subsequent approved revisions.
In addition to all other commitments contained in the physical security plan, the licensee shall ensure that whenever an emp1,oyee leaves the employment of i
TVA, all locks, keys, combinations, card keys, or related equipment used to l
control access to the Sequoyah Nuclear Plant protected area or vital areas to which that employee had access shall be changed.
i F.
Reactor Safety Methodoloay Applications Programs (Section 24.0)
TVA will provide a report prepared by the Kaman Sciences Corporation (KSC) on a full scale nuclear safety and availability analysis within six months from the date of the KSC report.
G.
This license is subject to the following additional conditi'on for the protection of the environment:
Before engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated l
by the CL aission, Tennessee Valley Authority will prepare and record l
an environmental evaluation of such activity. When the evaluation indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly l
greater than that evaluated in the Final Environmental Statement l
l
I.
- l prepared by the Tennessee Valley Authority and the Environmental Impact Appraisal prepared by the Coission in May 1979, the Tennessee Valley Authority shall provide a written evaluation of such activities and obtain prior approval from the Director, Office of Nuclear Reactor Regulation.
H.
If TVA plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the Sequoyah Nuclear Plant, the Commission shall be notified in writing regardless of whether the change affects the amount of radioactivity in j
the effluents.
l l
I.
TVA shall report any violations of the requirements contained in Sections 2.C(3) through 2.C.(17), 2.E, 2.F, 2.G, and 2H of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his designee, no later than the first working day following the violation with a written followup report within 14 days.
J.
TVA shall immediately 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 establisned by the Commission.
K.
TVA shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to co 'er public liability claims.
L.
This license is effective as of the date of issuance and shall expire May 27, 2010.
FOR THE NUCLEAR REGU'ATORY COMMISSION L
Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachinent:
- 1.
2.
Appendices A and B Technical Specifications Date of Issuance:
ATTACHMENT 1 CONSTRUCTION RELATED ITEMS TO BE COMPLETED This attachment identifies certain items which must be completed to the satisfaction of the NRC Office of Inspection and Enforcement in accordance with the schedule listed below. Tennessee Valley Authority shall not proceed beyond the authorized events without prior written authorization from the Office of Inspection and Enforcement.
Prior to Fuel Loading 1.
Complete all applicable preoperational testing, including the integrated test of the Engineered Safety Features Systems.
2.
Fully implement security plan, in particular, consider the containment as a vital area and meet all requirements for alarming normally unoccupied vital areas.
(Ref.10 CFR 573.55(d)(7), 573.55(d)(8), 573.55(e)(1)).
Prior to Initial Criticality 1.
Resoive construction deficiency EEB 8054, Failure of Generator to Supply Adequate Voltage to Safety-Related Boards.
(LII,81-02-37).
2.
Resolve construction deficiency NEB 8013, Limit Switch Actuator for Masoneilan Air-Operated Valves. (LII,81-20-05).
3.
Resolve construction deficiency NEB 8122, Power Operated Relief Val"e Operating Tine.
(LII, 81-20-19).
4.
Resolve construction deficiency NCR 28P, Inadequate Cladding Thickness on the 28-B Centrifugal Charging Pump Casing.
( LII, 81 21 ).
5.
Complete applicable preoperational testing and resolve significant test deficiencies. As of May 22, 1981, seventeen test procedures ha.ve not been started and four tests are in progress.
6.
Resolve IE Bulletin 79-14, Need for Seismic Reanalysis of As-built Safety-related Piping Systems.
7.
Determine the repeatability of test W-6.2, UHI Preoperational Test, and conduct testing as necessary. (UNR, 80-23-08).
~
8.
Verify adequacy of retest for adjusted Upper Head Injection flow control valves and perfom further testing as necessary. (UNR, 80-23-09, 80-23-10).
9.
Determine adequacy of specifications to ensure off-line sampling is effective for flushing.
(UNR, 80-23-12).
- 10. Resolve construction deficiency CEB 79-19, Containment Piping Support i
Design Basis.
(LII, 79-16-04).
l
. 12. Resolve construction deficiency MEB 79-4, High Flow Alarm in Essential Raw Cooling Water Piping.
(LII,79-07-10).
(LII, 81-01-03).
- 14. Resolve construction deficiency SWP 8023, Seismic Analysis for As-Built Safety-Related Piping Systems. (LII,81-02-25).
- 15. Resolve construction deficiency CEB 8039, Non-conservative Loads on Pipe Support Design Modifications.
( LII, 81 33 ).
- 16. Resolve construction oeficiency NEB 8115, Possible Error in Safety Injection Systen.Preoperational Test.
(LII, 31-20-12).
- 17. Resolve construction deficiency EEB 8111, relating to service rating for 460 Volt Motors. (LII, 81-20-21 ).
- 18. Resolve construction deficiency EEB 8115, 8034, Degraded Voltage Requirements for 460 Volt Motors.
(LII, 81-20-22, 81-02-17).
- 19. Resolve IE Bulletin 79-27, Loss of Non-class IE Instrumentation and Control Power System Bus.
- 20. Resolve IE Sulletin 80-06, Engineered Safety Features Reset Controls.
21. Resolve construction deficiency NEB 8017, CBCS Centrifugal Charging Pumps.
(LII, 81-02-06).
Prior to Reaching Full Power 1.
Resolve construction deficiency MEB 8006 R1, Excessive Pressure Drop Across Essential Raw Cooling Water Strainers.
(LII, 81-20-07).
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UNITED STATES NUCLEAR REGULATORY COMISSION DOCKET NO. 50-328 TENNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Facility Operacing License No. DPR-79, to Tennessee Valley Authority (licensee) which authorizes operation of the Sequoyah Nuclear Plant, Unit 2 (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.
The Sequoyah Nuclear Plant, Unit 2, is a pressurized water nuclear reactor located l
at the licensee's site in Hamilton County, Tennessee, about 9.5 miles northeast of Chattanooga. The license is effective as of the date of issuance.
The application for the license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission has determined that the issuance of this license will not result in any environmental impacts other than those evaluated in the Final Envir%menta?
Statement since the activity authorized by the license is encompasset by the overall l
action evaluated in the Final Environmental Statement.
a
- For further details with respect to this action, see (1) Facility Operating License No. DPR-79, complete with Technical Specifications; (2) the reports of the Advisory Comittee on Reactor Safeguards dated December 11,1979, July 15, 1990, September 8,1980, and January 31, 1981; (3) the Comission's Safety Evaluation Report (NUREG-0011) dated March 1979, Supplement No.1 dated February 1980, Supplement No. 2 dated August,1980, Supplement 3 dated September 1980, l
Supplement 4 dated January 1981, and Supplement 5 dated June 1981; (4) the Final Safety Analysis Report and amendments thereto; (5) the Final Environmental Statement prepared by Tennessee Valley Authority in July 1974; (6) the Commission's Environmental Imoact Appraisal dated May 1979; (7) NRC Flood Plain Review of Sequoyah Nuclear Plant Site dated July 18, 1980; and (8) Discussion of the Environmental Effects of the Uranium Fuel Cycle dated September 3,1980.
These items are available for public inspection at the Commission's Public Document Room,1717 H Street, N. W., Washington, D. C., and the Chattanooga Hamilton County Bicentennial Library,1001 Broad St,r,eet, Chattanooga, Tennessee 37402. A copy of Facility Operating License No. DPR-79 may be obtained upon request aadressed to the U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention:
Director, Division of Licensing. A copy of item (3) may be purchased at current rates from the National Technical Information Service, Department of Commerce, 5285 Port Royal Road, Springfield, Virginia 22161, and through the NRC GPO sales program 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 day of June,1981.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor Adensam, Acting Chief Licensing Branch No. 4 Division of Licensing
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UNITED STATES
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WASHINGTON, D. C. 20555
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Docket No. 50-328 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower 11 Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
SEQUOYAH NUCLtAR PLANT, UNIT 2 - ISSUANCE OF FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission has issued the enclosed Facility Operating License No. DPR-79 to the Tennessee Valley Aui.hority for the Sequoyah Nuclear Plant, Unit 2, located in Hamilton County, Tennessee. License No. DPR-79 authorizes operation of the Sequoyah Nuclear Plant, Unit 2, at five percent power (170 megawatts thermal) upon completion of certain related construction items.
The tem of the license shall be for one year. Authorization to operate beyond five percent is still under consideration by the NRC. The issuance of this license authorizing operation at five percent of full power is without prejudice to future consideration by the Commission with respect to operation at power levels in excess of five percent.
Also enclosed is a copy of a related Federal Register notice which has been forwarded to the Office of the Federal Register for publication.
Two signed originals of Amendment No. 7 to Indemnity Agreement No. B-82 which covers the activities authorized under License No. DPR-79 are also enclosed.
P' lease sign and return one copy to this office.
Sincerely, l
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
1.
Facility Operating License No. DPR-79 2.
Federal Register Notice 3.
Amendment 7 to Indemnity Agreement B-82 cc w/ enclosures:
See next page
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NUCLEAR REGULATORY COMMISSION h,I j
WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 1
FACILITY OPERATING LICENSE License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) having found that:
A.
The application for licenses filed by the Tennessee Valley Authority 1
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.
Constructics of the Sequoyah Nuclear Plant, Unit 2 (the facility),
has been suostantially completed in conformity with Provisional l
Construction Permit No. CPPR-73 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 I
amended, the provisions of the Act, and the regulations of the l
Comission; D.
There is reasonable assurance: (i) that the activities authorized by t
this operating license can 'oe 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 Commission 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 Commission's regulations set forth in 10 CFR Chapter 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 comon defense and security or to the health and safety of the public;
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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 Operating License No. DPR-79, 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 applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct, and special l
nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Pursuant to approval by the Nuclear Regulatory Commission at a meeting on June 17, 1981, Facility Operating License No. DPR-79 is hereby issued to the Tennessee Valley Authority to read as follows:
A.
This license applies to the Sequoyah Nuclear Plant, Unit 2, 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.
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B.
Subiect 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 Utilizatioh 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 limitations 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 70, 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 inonitoring equipment calibration, and as fission detectors in amounts as required;
- See 10 CFR S 51.56
. (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 special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (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 nay be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to ai; applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to ti a additional conditions specified or incorporated below:
(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 5 percent (170 megawatts thermal ). Fuel loading and operation of the facility is subject to compliance with construction items listed in Attachment 1.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B attached hereto are hereby incorporated in this license. The Tennessee Valley Authority shall operate the facility in accordance with the Technical Specifications.
(3)
Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading
.nitial test program (set forth in Section 14 of Tennessee Valley Autnority's Final Safety Analysis Report, as amended), without l
making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
a.
Elimination of any test identified in Section 14 of TVA's Final Safety Anc' ais Report as amended as being essential; l
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; c.
Performance of any test at a power level different from that described in the program; and l
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. d.
Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized power level).
(4) Monitoring Settlement Markers (Section 2.6.3)
TVA shall monitor the settlement markers along the ERCW conduit for the ner ERCW intake structure for a period not less than three years from tr.e date of this license. Any settlement greater than 0.5 inches that occurs during this period will be evaluated by TVA and a report on this matter will be submitted to the NRC.
(5) Environmental Qualification (Section 7.2.2) a.
No later than June 30, 1982, TVA shall be in compliance with the requirements of NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," for safety-related equipment exposed to a harsh environment.
b.
Complete ad auditable records must be available and maintained at a central location which describe the environmental qua!ifica-i l
tion method used for all safety-related electrical equipment in l
sufficient detail to document the deoree of compliance with the 00R Guidelines or NUREG-0588. Such records should be updated and maintained current as equipment is replaced, further tested, or othemise further qualified to document complete compliance by June 30,1982.
- c. 'Within 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (i) provide missing documentation identified in Sections 3 and 4 of the equipment qualification safety evaluation which will demonstrate compliance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30,198L.
(6) Fire Protection System (Section 9.5) a.
TVA shall maintain in effect and fully implement all provisions of the approved fire protection plan and_the NRC staff's Fire Protection Review in Supplements 1, 2 and 5 to the Sequoyah Safety Evaluation Report. By July 1981, TVA shall implement the following three items which deal with the ERCW supply: (a) enclose the necessary expcsed conduit with a 1-1/2-hour fire barrier; (b) reroute train B ERCW pump and transformer power cables to obtain a minimum 20-foot separation from train A; and (c) enclose the ERCW junction box with a 1-1/2-hour fire barrier.
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. b.
After initial criticality of Unit 2 and prior to the completion of item (a) above, TVA shall provide:
- 1) a continuous fire watch in the area of the ERCW junction box on elevation 690.0 of the auxiliary building.
- 2) a roving fire watch in the ar ? of conduits which exit the top of the junction box, pass through floor elevation 714.0, and terminate on floor elevation 734.0.
c.
TVA shall replace the control room ceiling panels with panels acceptable to NRC by September 1,1981.
d.
By October 1,1981, TVA shall submit a report that identifies and justifies differences between existing or proposed fire protection features and these features specified in Sections III.G, III.J, III.L, and III.0 of Appendix R to 10 CFR Part 50.
TVA shall implement any fire protection features found appropriate by the NRC on a schedule consistent with that required for other operating reactors.
(7) Compliance with Regulatory Guide 1.97 By June 30, 1981, TVA shall submit a proposal, including an implementation schedule, for compliance with R.G.1.97.
(8) NUREG-0737 Conditions (Section 22.2)
Each of the follcwing conditions shall be completed to the satisfaction of the NRC by the times indicated:
a.
Shift Technical Advisor (Section 22.2, I.A.l.1)
TVA shall provide a fully-trcined on-shift technical advisor to the shift supervisor.
b.
Independent Safety Engineering Group (Section 22.2, I.BJ.2)
TVA shall have an onsite Independent Safety Engineering Group.
c.
Procedures for Verifying rnrrect Performance of Operating Activities (Section 22.2, I.G.6)
Procedures shall be available to verify the adequacy of the operating activities.
. d.
Training During Low-Power Testing (Section 22.2, I.G.1)
Licensed operators shall complete simulator training for natural circulation conditions. One experienced operator trained on Unit 1 low power testing for natural circulation operation shall be assigned to each shift. Requirement remains in effect until TVA submits a report and NRC agrees with findings that an acceptable level of training and experience on Unit 2 has been attained.
e.
Reactor Coolant System Vents (Section 22.2, II.B.1)
By July 1,1982, TVA shall install reactor coolant system and reactor vessel head highpoint vents that are remotely operable from the control room.
f.
Pou. Accident Sampling (Section 22.2, II.B.3)
By January 1,1982, TVA shall complete corrective actions needed to provide the capability to promptly obtain and perform radioisotopic and chemical analyses of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure.
g.
Hydrogen Control Measures (Section 22.2, II.B.7)
(1) For operation of the facility beyond January 31,1982, the Commission must confinn that an adequate hydrogen control system for the plant is installed and will perform its intended function in a manner that provides adequate safety margins.
(2) During the interim period of operation, TVA shall continue a research program on hydrogen control measures and the effects of hydrogen burns on safety functions and shall submit to the NRC quarterly reports on that research program.
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(a) TVA shall amend its research program on hydrogen control measures to include, but not limited to, the following l
items:
- 1) Improved calculational methods for containment temperature and ice condenser response to hydrogen l
combustion.
- 2) Research to address the potential for local detonation.
- 3) Confirmatory tests on selected equipment exposed to hydrogen burns.
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. 4) New calculations to predict differences between expected equipment temperature environments and containment temperatures.
- 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 the January 31, 1982 deadline, Section (17)h.(1) of tne license.
h.
Relief and Safety Valve Test Requirements (Section 22.2, II.D.1)
TVA shall coniann to the results of the EPRI test program.
Documentation for qualifying the reactor coolant system relief and safety valves under expected operating conditions for design basis transient accidents is to be completed by October 1981. Documentation on piping and supports is required by January 1982. Block valves are to be qualified by July 1982.
1.
Containment Isolation Dependability (Section 22.2, II.E.4.2)
TVA shall limit the purge valve openings to less than or equal to 50 degrees.
j.
Additional Accident Monitoring Instrumentation (Section 22.2, II.F.1)
By January 1,1982, TVA shall install continuous indication in the control room of the following parameters:
(1) Containment radiation monitors.
(2) Noble gas effluent from each potential release point.
k.
Instruments for Inadequate Core Cooling (Section 22.2, II.F.2)
(1) TVA shall provide a reactor vessel water level instrumentation system by January 1,1982.
(2) TVA shall submit a proposal for upgrading the incore thermocouple system in June 1981. TVA shall upgrade the incore thermocouple system by January 1,1982.
1.
Voiding in Reactor Coolant System (Section 22.2, II.K.2.17)
TVA is participating in the hstinghouse owners group effort on this item and shall conform to the results of this effort. The analysis will be submitted by January 1,1982.
. Sequential Auxiliary Feedwater Flow Analysis (Section 22.2, II.K.2.19) m.
TVA is participating in the Westinghouse owners group effort on this item and shall conform to the results of this effort.
The analysis will be submitted by July 1,1982.
n.
Calculations for Small-Break LOCAs (Section 22.2, II.K.3.30 and II.K.3.31)
TVA is participating in the Westinghouse owners group effort for this item and shall confonn to the results of this effort.
The analysis for model justification will be submitted by January Upgrade Emergency Preparedness (Section 22.2, III. A.l.1) o.
TVA is required to have a prompt notification system installed and operational by July 1,1981.
p.
Upgrade Emergency Support Facilities (Section 22.2, III. A.l.2)
(1) TVA shall have in operation the upgraded emergency support facilities by October 1,1982 consistent with the guidance of NUREG-0696 and in accordance with the provisions of NRC letter to TVA dated March 19, 1981.
(2) TVA shall maintain interim emergency support facilities (Technical Support Center, Operations Support Center and the Emergency Operations Facility) until the final facilities are complete.
q.
Long-Tenn Emergency Preparedness (Section 22.2, III. A.2)
Functional description of up' graded capabilities shall be provided by January 1,1982. Installation of hardware and software shall be completed by July 1,1982. Full operational capability is required by October 1,1982.
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 Evaluation Report, Supplements No.1 and No. 5.
These exemptions are authorized by law and will not endanger life or property or the coninon defense and security and are otherwise in the public interest. Therefore, these examptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission.
. l A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 5, Section 6.2.4.
This exemption is authorized by law and will 9t endanger life or property or the common defense and security and is otherwise in the public interest. The exemption, therefore, is hereby granted and shall remain in effect through the first refueling outage as discussed in Section 6.2.4 of Supplement 5 to the Safety Evaluation Report.
The granting of the exemption is authorized with the issuance of the Facility Operating License. The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
E.
The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, guard training and qualification plan, and safeguards contingency plan, including amendments made pursuant to the authority of 10 CFR 550.54(p). The approved plans consist of 10 CFR $2.790(d) informatir n collectively entitled:
" Physical Security Plan for the Sequoyah Nuclear P11nt", dated August 25, 1978, as revised on April 2,1979, June 29, 1979, Septercher 19, 1979, and December 16,1980; "Sequoyah Nuclear Plant Security Personnel Training and Qualifications Plan" dated August 17, 1979, as revised January 24,1980, May 21,1980, October 1,1980, March 9,1981, and as amended by subsequent approved revisions; and the "Sequoyah Nuclear Plant Safeguards Contingency Plan", dated March 1,1979, as revised September 1, 1979, April 15,1980, December 21,1980, March 30,1981, and as amended by subsequent approved revisions.
In addition to all other comitments contained in the physical security plan, the licensee shall ensure that whenever an employee leaves the employment of TV A, all locks, keys, combinations, card keys,' Or related equipment used to control access to the Sequoyah Nuclear Plant protected area or vital areas to which that employee had access shall be changed.
F.
Reactor Safety Methodology Applications Programs (Section 24.0)
TVA will provide a report prepared by the Kaman Sciences Corporation (KSC) on a full scale nuclear safety and availability analysis within six months from the date of the KSC report.
G.
This license is subject to the following additional condition for the protection of the environment:
Before engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated by the Commission, Tennessee Vallef Authority will prepare and record an environmental evaluation of such cctivity. When the evaluation indicates that such activity may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated in the Final Environmental Statement l
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, prepared by the Tennessee Valley Authority and the Environmental Impact Appraisal prepared by the Commission in May 1979, the Tennessee Valley Authority shall provide a written evaluation of such activities and obtain prior approval from the Director, Office of Nuclear Reactor Regulation.
H.
If TVA plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the Sequoyah Nuclear Plant, the Commission shall be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.
I.
TVA shall report any violations of the requirements contained in Sections 2.C(3) through 2.C.(8), 2.E, 2.F, 2.G, and 2H of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his designee, no later than the first working day following the violation with a written followup report within 14 days.
J.
TVA shall immediately 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.
K.
TVA shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
L.
This license is effective as of the date of issuance and shall expire one year from date of issuance.
)
FOR THE NUCLEAR REGULATORY COMMISSION Harold R. Denton, Director Office of Nuclear Reactor Regulation
Attachment:
- 1.
2.
Appendices A and B Technical Specifications Date of Issuance:
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ATTACHMENT 1 CONSTRUCTION RELATED ITEMS TO BE COMPLETED This attachment identifies certain items which must be completed to the satisfaction of the NRC Office of Inspection and Er.forcement in acco.-dance with the schedule listed bel ow. Tennessee Valley Authority shall not proceed beyond the authorized events without prior written authorization from the Office of Inspection and Enforcement.
Prior to Fuel Loading 1.
Complete all applicable preoperational testing, ixluding the integrated test of the Engineered Safety Features Systems.
2.
Fully implement security plan, in particular, consider the containment as a vital area and meet all requirements for alarming nonna11y unoccupied vital areas.
(Ref.10 CFR 573.55(d)(7), $73.55(d)(8), 573.55(e)(1)).
Prior to Initial Criticality 1.
Resolve construction deficiency EEB 8054, Failure of Generator to Supply Adequate Voltage to Safety-Related Boards.
(LII,81-02-37).
2.
Resolve construction deficiency NEB 8013, Limit Switch Actuator for Masoneilan Air-Operated Yalves.
(LII, 81-20-05).
3.
Resolve construction deficiency NEB 8122, Power Operated Relief Valve Operatir.g Time.
( LII, 81 19).
4.
Resolve construction deficiency NCR 28P, Inade'quate Cladding Thickness on the 28-B Centrifugal Charging Pump Casing.
(LII, 81-02-21 ).
5.
Resolve IE Bulletin 79-14, Need for Seismic Reanalysis of As-built Safety-related Piping Systems.
6.
Determine the repeatability of test W-6.2, UHI Preoperational Test, and conduct testing as necessary.
(UNR,80-23-08).
7.
Verify adequacy of retest for adjusted Upper Head Injection flow control valves and perform further testing as necessary.
(UNR, 80-23-09, 80-23-10).
8.
Determine adequacy of specifications to ensure off-line sampling is effective for flushing. (UNR,80-23-12).
9.
Resolve construction deficiency CEB 79-19, Containment Piping Support Design Basis.
(LII, 79-16-04).
. 10. Resolve construction deficiency MEB 79-4, High Flow Alarm in Essential Raw Cooling Water Piping. (LII, 79-07-10).
(LII, 81-01-03).
- 12. Resolve construction deficiency SWP R323, Seismic Analysis for As-Built Safety-Related Piping Systems. (LII, 81-02-25).
- 13. Resolve construction deficiency CEB 8039, Non-cons?rv'tive Loads on Pipe Support Design Modifications.
(LII, 81-02-33).
- 14. Resolve construction deficien;y NEB 8115, Possible Error in Safety Injection System Preoperational Test.
( LII, 81 12).
- 15. Resolve construction deficiency EEB 8111, relating to service rating for 460 Volt Motors. (LII, 81-20-21 ).
- 16. Resolve construction deficiency EEB 8115, 8034, Degraded Voltage Requirements for 460 Volt Motors.
(LII, 81-20-22, 81-02-17 ).
- 17. Resolve IE Bulletin 79-27, Loss of Non-class IE Instrunentation and Control Power System Bus.
- 18. Resolve IE Bulletin 80-06, Engineered Safety Features Reset Controls.
- 19. Resolve construction deficiency NEB 8017, CVCS Cantrifugal Charging Pumps.
( LII, 81 06).
- 20. Complete applicable preoperational testing anc resolve significant test' deficiencies.
i
UNITED STATES NUCLEAR REGULATORY C0petISSION DOCKET NO. 50-328 TENNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Comission 'the Commission) has issued Facility Operating License No. DPR-79, to Tennessee Valley Authority (licensee) which authorizes operation of the Sequoyah Nuclear Plant, Unit 2 (the facility), at reactor core power levels not in excess of 170 megawatts thermal (5 percent power) in accordance with the provisions of the license and the Technical Specifications.
The Sequoyah Nuclear Plant, Unit 2, is a pressurized water nuclear reactor located at the licensee's site in Hamilton County, Tennessee, about 9.5 miles northeast of Chattanooga. The license is effective as of the defn of issuance for a period of one year.
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 Commission has made appropriate findings as required by the Act and the Commission'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 FEDEilAL REGISTER on March 25,1974 (39 FR 11131).
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 l
action evaluated in the Final Environmental Statement.
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i For further details with respect to this action, see (1) Facility Operating License No. DPR-79, complete with Technical Specifications; (2) the reports of l
the Advisory Comittee on Reactor Safeguards dated December 11,1979, July 15, 1980, September 8,1980, and January 31, 1981; (3) the Commission's Safety Evaluation Report (NUREG-0011) dated March 1979, Supplement No.1 dated February l
1980, Supplement No. 2 dated August,1980, Supplement 3 dated September 1980, l
Supplement 4 dated January 1981, and Supplement 5 dated June 1981; (4) the Final 1
Safety Analysis Repc.'t and amendments thereto; (5) the Final Environmental I
Statement prepared by Tennessee Valley Authority in July 1974; (6) the Comission's Environmental Impact Appraisal dated May 1979; (7) NRC Flood Plain Review of Sequoyah Nuclear Plant Site dated July 18,1980; and (8) Discussion of the Environmental Effects of the Uranium Fuel Cycle dated September 3,1980.
These items are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., Washington, D. C., and the Chattanooga Hamilton County Bicentennial Library,1001 Broad Street, Chattanooga, Tennessee 37402. A copy of Facility Operating License No. DPR-79 cay be obtained upon request l
addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention:
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Director, Division of Licensing. A copy of item (3) may be purchased at current rates from the National Technical Information Service, Department of Commerce, 5285 l
Port Royal Road, Springfield, Virginia 22161, and through the NRC GP0 sales program by writing to U.S. Nuclear Regulatory Comission, Attention: Sales Manager, Washington, l
D. C. 20555. GP0 deposit account holders can call 301-492-9530.
l Dated at Bethesda, Maryland, this day of June,1981.
FOR THE NUCLEAR REGULATORY CDMMISSION
(
t Elinor Adensam, Acting Chief Licensing Branch No. 4 Division of Licensing
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TRANSMITTAL TO:
/X7 Document Control Desk, 016 Phillips ggg/
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ADVANCED COPY TO:
O The Public Document Room j iT.,nr e
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June 18, 1981
- 4 c) g, A&rce Attached are the PDR copies of a Commission meetingQ,
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are being forwarded for entry on the Daily Accession $ [T transcript /s/ and related meeting document /s/.
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No
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other distribution is requested or required.
Existing g,.y DCS identification numbers are listed on the individual 6
documents wherever possible.
e 1.
Transcript of:
Discussion and Possible Vote on Operating License for Sequoyah-2.
June 17, 1981.
(1 copy) a.
Memo from Com. Bradford to the other Commissioners L
dated June 15, 1981, subj:
no subject line. (1 copy) b.
Meeting handout:
Sequoyah Unit No.
2, License I
Revision.
(1 copy)
%i c.
Meeting handout:
Sequoyah Unit 2, Status of Construction Items.
(1 copy) d.
Memo from W. Dircks to the Commissioners dated
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June 12, 1961, Subj:
Startup Schedule'for Q
Sequoyah, Unit No.
2.
(1 copy) e.
Memo to H.G.Parris, TVA from Darrell Eisenhut undated, Subj:
Sequoyah Nuclear Plant, Unit 2 - Issuance of Facility Operating License (1 copy)
(Full Power) f.
Memo to H.G.Parris, TVA from Darrell Eisenhut, undated, Subj:
Sequoyah Nuclear Plant, Unit 2 - Issuance of Facility Operating License (Low Power)
(1 copy) b jake own b
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of the Secretary i
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UNITED STATES o
,f i NUCLEAR REGULATORY COMMISSION
\\ h Jf' j WASHINGTON D. C. 20555
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OFFICE OF THE SECRETARY l
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NOTE T0: Mike Collins FROM:
Tom Combs ds Attached 454 copy of the transcripts and supporting documents from e Comission meetingsto be entered into the DCS. t dopy,es hak already been forwarded to the PDR.
No further distribution is required.
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