ML20031C862
| ML20031C862 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/15/1981 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031C864 | List: |
| References | |
| NUDOCS 8110090049 | |
| Download: ML20031C862 (14) | |
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TEMESSEr. VALLLY Aultf0RITY 00C(ET NO. 50-328
$EQUO'thn.9dCLEAR PLANT, UNIT 2 FACILIT f OPERATl!G LICLNSE License No. DPR-79 Amendment No. 2 1.
The Nuclear Regasatory Comiaission (tne Coanission or the NRC) has found that; a
A.
The application for license filed by the Tennessee Valley Authority (the licensee or TVA) conplies with the standards and requirements of the Atomic Enargy Act of 1954, as amended (the Act), and the
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Commission's regulations set fortn in 10 CFR Chapter 1, and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Sequoyah Nu: lear Plant, Unit 2 (tne facility),
has been substantially cor.pleted in conforuity with Provisional Construction Permit No. CPPR-73 and the applicatien, as araended, the provisions cf the Act, and the regulations of the Comaission; C.
The facility will operate infconformity with the application, as duended, the pravisions of tha Act, and tne regulations of the Con-mission; U.
ihere is rer 3 assurance; (1) tnat the activities authorized by this araend(
.. ting license can be conducted without endangering the health anu safety of the public, and (ii) that such act1vities A
will be conducted in compliance with the regulations of the Cocais-sion set forth in 10 CFR Chapter I; L.
The Tennessee Valley Authority is technically and financially qualified to engage in the activities authorized by this anended operating license in accordance witn the Comaission's regulations set forth in 10 CFR Chapter I; F.
The Tennessee Valley Authority has satisfied tne applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", of the Co;aaission's regulations; G.
The issuance of this auendec license will not be inimical to the coumon i
defense and security or to the health and safety of the public; 8110090049 810915 PDR ADOCK 05000328 P
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. 11.
Af ter weighing the environmental, economic, tecnnical, and other benefits of the facility against environmental and otner costs and considering available alternatives, the issuance of Amendment 2, subject to the conditions fcr protection of tne environment set forth herein, is in accordarce with 10 CFR Part 50, Appendix D*,
of the Coumission's regulations and all applicable requirements have been sdtisfied; and I.
The receipt, possession, anc. use of 50urce, byproduct, and special nuclear material as authorized by this amended license will he in accordance with tne Cormission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Pursuant to approval by the huclear Regulatory Coaatssion at e meeting on September d.1981, Amendaent No. 2 ansads Fucility Operating License No. DPR-79 issued to the Tennessee Vallcy Authority in its entirety to read as follows:
A.
This amenced license applies to the Sequoyah Nuclear Plant, Unit 2, a pressurized water nuclear reactor and associated equipment (the facility), owned by tne 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 sup;'lemented and amended, and the Final Environmental Statement prepared by die Tennessee Valley Authority.
B.
Subject to the conditions and requirements incot norated herein, the Cat.ission hereby licenses the lennessee Valley uthority:
(1) Pursuant to Section 104(D) of the Act and 10 CFR Part 50,
" Licensing of Production and Utilization Facilities", to possess, use, and operate the facility at tne designated location in llamilten County, Tennessee, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to tne Act anc 10 CFR Part 70, to receive, possess, and use at any time special nuclear naterial as reactor fuel, in accordance with tne limitations for storage and amounts required for reactor operation, as described in the Final Satety Analysis Report, as suppler.cnted and amended; (3) Pursuant to the Act and 13 CFR Parts 30, 40, and 70, to receive, possess, nd use at any time any byproduct, source and special nuclear uaterial as sealed neutron sources for reactor startup, sealeo sources for reacter instru:nentation and radiattun monitoring equipment calibration, and as fission detectors in araounts as required;
. (4) Pursuant to tne Act and 10 CFR Farts 30, 40, and 70, to receive, possess, and use in amounts as required any byprcduct, ource or special nuclear inaterial without restriction to cneai<:al 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 end special nuclear naterials as.may be produced by the operation of the facility.
C.
This amended license snall be deemed to contain and is subject to the conditions specified in the Cowission.'s regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in ef fect; :ind is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The Tennessee Valley Authortts is autnorized to operate the facility at reactor core power levels not in excess of 3411 megawatts 5,nermal.
Operation of tne facility is subject to compliance with the construc-tion ite a listed in Attachment 1.
(2)
Technical Specifications Tne 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 Progru The Tennessee Valley Autnority shall conduct the post-fuel-lodding initial test prograrr, (set forth in Section 14 of Tennessee Valley Authority's Final Sofety Analysis Report, as amended), without making any saajor modifications of this program unless modifications have been identified and have received prior URC approval. Major modifications are defined as:
a.
Elimination of any test identified in Section 14 of TVA's Final Safety r.nalysis Report, as arnenced, as being cssential; b.
Modification of test objectives, metnods, or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report, as auended, as being essential;
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c.
Performance of any test at a power level of fferent f ro:a tnet cecri6 u in-pe pregrem, gid i
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Failure to complete any tests included in the described program (planned or scheduled) for power levels up to the authorized power level.
(4) llonitoring Settlement liarkers (SLR/S5LP. Section 2.6.3)
TVA shall continue to nonir,or the settlement markers along the ERCW conduit for tne new LkCW intake structure for a period not less than three years from the date of this license.
Any settlement greater than 0.5 inches that occurs during this period will be evaluated by TVA ano a report on this matter will be submitted to the LRC.
(5)
Tornado liissiles (bection 3.5)
Prior to startup af ter tne first ref ueling of the facility, TVA shall recontin:i to the satisf action of the WRC that adequate tornado protection is provided for the 460 V transtorner ventilation systems.
(6) _ Design of Seismic Category Structures (Section 3.8)
Prior to startup rollowing the first refueling, TVA shall evaluate dll seismic Category 1 Masonry Walls to final hRC Criteria and iuplement kRG required modificetions that are indicated by tnat evaluttion.
(7) Low Temperature overpressure Prnta ction s aection 5.2.2)
Prior to startup af ter the first refueling, TVA shall install an overpressure uitigation system wnicn meets NRC requirements.
(8) Stea.n Generator Inspection (Section 5.3.1)
Prior to start-up af ter the first r tuoling, TVA shall install inspection ports in each steau generotur or have an alternative for inspection that is acceptable to the HaC.
(9) Lontainment isolation Systens (bection 6.2.4)
Prior to startup af ter tue first refueling, TVA snall codify to the satisfaction of the udC the one-inch chemical feed lines to the main and auxiliary fecawater lines for compliance wi h GDC 57.
t (10)
Environmental qualification (section 7.2.2) a.
Ho later tnan June Ju,1982, TVA shall be in compliance with the requirements of huntb-05dd, " Interim Staf f Position un Envirenwental Qualitication of Safety-Related Electrical Equipment," for safety-related equipmen. exposed to a harsh environnent.
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Couplete and auditable records must be available and maintained at a central location which describe the environmental qualifi-cation method used for all safety-related electrical equipnent in suf ficient detail to document tne degree of compliance with the DOR Guidelines or udi<LL-0588. Such records should be updated and uaintained current as equipment is replaced, further tested, or otherwise further quali tied to document complete compliance by June 30, 1982.
Witnin 90 days of receipt of the equipment qualification safety c.
evaluation, the 11cer.see shall either (1) provide missing doc-uacntation identified in Sections 3 and 4 of the equipment qualification safety evaluation which will demonstrate compli-ance or the applicabla equiprent with NURLG-0588, or (ii) connit to corrective actions which will result in documentation of compliance of applicable equipment with NuitEG-OSdB no later than
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June 30, 1932.
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(11) Requtrements For tlodification To or Addition of Instrumentation l
Ano t,ontrols bection /.J.2)
Prior to startup af tcr first refuelin9, TVA shall have installed a.
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instruuent downscale failure alarns for the effluent monitoring instruuentation channels for radioactive gaseous and radioactive I
liquid effluents. ;1odifications to procedures and Techrt;al f
Specifications 3.3.3.9 and 3.3.3.10 shall nave been completed, i
b.
Prior to startup after the first refueling, TVA shall have
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received udG approval of an additional operable level of over/
undervoltage protection including associated Technical Specifi-cations. The level of protection troa tne effects of power P
transients on safety-related equipment provided by Part I of tne staf f's "cegraded Grid Voltage Position", or equivalent, g
is required.
(12) Dicsel Generator rieliability (Section u.3.1)
Prior to op ration f ollowing the first refueling, TVa shall implement the fallowing design and procedure modifications as outlined in l
Section 8.3.1 of SER Supplement ho. 2.
These include: (a) hoisture in Air Storting System; (b) Turbocharger Gear Drive Problea; and l
(c) Personnel Training.
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-o-2 (13) Fire Protection Systeo (Section 9.b)
TVA shall maintain in ef fect and fully implement all provisions a.
of the approved fire protection plan and the likC staff's Fire Protection Review in tne Sequoyan Safety Evaluation Report and Supplements.
b.
TVA shall replace the control roua ceiling panels with panels dCCeptable to naC by Septeaaer 30, 1961.
c.
TVA shall conply with Section Ill.G. Ill.J Ill.L and 111.0 of Appendix R of 10 CFR 50, except utiere IEC has approved devia-tions, on a schedule consistent witn tha, required for other operating reactors. By October 1,1991 TVA shall submit a report tnat iaentifies and justifies dif ferences between existing or proposed fire protection features and those fea-tures specitiea in Section Ill.G Ill.J Ill.L and 111.0 of Appendix R to 10 CFR Part 50.
(14) Loupliance Witn Regulatory Guide 1.97 TVA shall implement modifications necessary to comply witn Revision 2 of Regulatory Guide 1.97, "Instrunentation for Lignt Water Cooled nuclear Power Plants to assess Plant Conditions During and Following an Accioent," dated Deceuber 1960, by June 1983.
(15) Corrosion or Carbon Steel Piping TVA shall carry out a surveillance progran on corrosion of carbon steel piping in accordance witn TVA document SQRD-50-326/81-10 dated August 25, 1901, and procedures for implementation are to De sub-uitted for NRC concurrence by October 15,19d1.
(16) fiuhtL-0/37 Londitions (Section 22.2)
Each of tne folloaing conditions snali also De performed to the sat-isfaction of tote I;RC:
d.
Shii t TeCuniCal Advisor (Section 22.2, l.h.l.l)
TVA snall provide a fully-trained on-shift technical advisor to the shif t superviser, b.
Independent Safety Engineering Group (Section 22.2, I.B.l.2)
TVA shall have an onsite Indepeedent Safety Engineering Group.
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Procedures for Veritying Correct Performance of Operating Activ-ities (Section 22.2, 1.C.0)
Procedures shall be availaole to verity the adequacy of the operating activities.
d.
Control Room Design (Section 22.2, I.D.1)
Prior to startup after first refueling of Unit 1 or Unit 2, whichever occurs first, TVA shall complete the detailed Control Room Design Review. As part cf this review, TVA shall consider benefits of installing data recording and logging equipr.sent in the control room to correct the deficiencies associated with the trending of important paraineters on strip chart recorders used in the control room.
e.
Training During Low-Power Testing (Section 22.2, I.G.1)
One experienced operator trained on Unit I low power testing for natural circulation operation shall be assigned to each shif t on this facility. This requirement snali remain until TVA submits a report, and iMC agrees with findings, that an aCC9ptable level of training ar.d experience on Unit 2 nas been attained.
f.
Reactor Coolant System Vents (Section 22.2, II.d.1)
At the first outage of sufficient duration, but no later than startup following first refueling outage. 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. 11.B.3)
At the first outage of sufficient duration, but no later tnan startup following first refueling outage, TVA shall complete corrective actions needed w provide the capability to proupti,r obtain and perforu radioisotopic and chemical analyses of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure.
h.
liydrogen Control Measures (Se:tton 22.2, II.B.7)
(1) Prior to startup following the first refueling outage, the Commission must confirm that an adequate nydrogen control system for the plant is installed and will perform its intended function in a manner tnat provides adequate safety margins.
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-a-(2) During the interia periou of operation, TVn snall continue a research prograan on tydrogen control measures and the effects of tydrogen burns on safety functions and snall submit to the hRC quarterly reports on that research program.
(a) TVA snall amend its research progran on hydrogen control measures to include, but not be limited to, the following i te.as :
- 1) Improved calculational iaethods for contairemnt temperature and ice condenser response to hydrogen conaustion.
- 2) Researcn to address the potential for local detonation.
- 3) Confiraatory tests on selected equipment exposed to hydrogen burns.
il New calculations to predict dif ferences between expected equipment teuperature environments and containment tenperatures.
- 5) Evaluate and resolve any anoiaalous results occurring during tne course of its ongoing test program.
(b) A schedule for confirmatory tests shall be proviced by TVA consistent with the requirement to meet section (16}n.(2) of the license.
1.
nelief and S!'ety Valve Test kequirements (Section 22.2, :1.D.1)
TVA snall conform to tne results of the EPal test prograu.
TVA shall provide documentation for qualifying (a) reactor coolant systea relief and safety valves, (b) piping and supports, and (c) block valves in accordance with the review schedule given in 5LCY 61-491 as approved by tne Couaission.
J.
Auxiliary f eeawater (Section 22.2, II.E.1.1)
Prior to exceeding five percent power, auxiliary feedwater pump endurance tests will be completed. A report shall be submitted to hkC within 30 days af ter all tests are completed.
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Containment Isolation Uependability (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 tionitoring Instruaentation (Section 22.2, 11.t.1)
(1)
TVA snall install interim noble gas ronitors at the first outage of sufficient duration.
(2) At the first outage of suf ficient duration, but no later than startup tollowing the first refueling outage, TVA shall install the following qualified monitoring instru-menta ti on-(a)
Integrated monitoring assembly which will accomplish particulate, iodine and noble gas monitoring.
(b) Containment high range radiation monitor.
(c) Containment pressure monitor.
(d) Containment water level monitor.
(e) Containment hydrogen monitor.
a.
Instruments for Inadequate Core Cooling (Lection 22.2, II.F.2)
(1) By Jt.iuary 1,1982, TVA shall install a backup indication for incore tnermocouples. This display shall be in the control rosa and cover tne temperatura range of 200 F -
2000 F.
(2) At tne first outage of sufficient duration, but no later than startup following first refueling outage TVA shall install reactor vessel water level instrumentation and the system will meet seismic and environmental require-3 ments.
n.
Voiding in Reactor Coolant System (Section 22.2. II.K.2.17)
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 to NRC by January 1,1982.
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Sequential Auxiliary Feedwater flow Anslysis (Section 22.2, II.K.2.19)
TVA is participating in the Westinghouse owners group effort on this item and shall conform to the results of this effo*t.
Tne analysis will be submitted to HRC by July 1,1982.
p.
Calculations for Small-Break LOCAs (Section 22.2 II.K.3.30 and ll.K.J.3l)
TVA is participatinj in the Westinghouse owners group effort for this iten and shall conform to the results of this effort.
Tne analysis for model justification will be submitted to HRC by January 1,1982.
q.
Upgrade Emergency Support Facilities (Section 22.2, Ill. A.I.2)
(1) The installation of the TSC shall be completed prior to startup after the first refueling.
However, if an outage scheduled to last more than five weeks occurs af ter Hay 1, 1962, installation of the necessary modifications to the control room and plant instrumentation will be completed at tnat time and tne TSC hardware installation will be completed witnin eleven weeks of the start of this sched-uled outage.
(2)
TVA shall maintain interin emergency support facilities (Technical Support Center, Operations Support Center and the Emergency Operations Facility) until the final facil-ities are caaplete.
r.
Long-Term Emergency Preparedness (Section 22.2, III.A.2)
Additional implementation dates for the iaeteorological program are:
(1) Functional description of upgraded capabilities shall be provided by January 1,1962.
(2)
Installation of hardware and sof tware shall be completed by July 1,1982.
(3) Full operational capability is required by October 1,1982.
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Primary Coolant Outside Containment (Section 22.2, Ill.D.I.1)
Prior to exceeding 5 percent power level, TVA is required to couplete the leak tests on Unit 2, and results are to be sub-witted within 30 days from the co.apletion of the testing.
D.
Fxemptions froa 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. I and rio. 5.
These exemptions are autnorized by law and will not endanger life or property or the comon defense and security and are otherwise in the public interest. Therefore, these exemptions are hereoy granted. Tne f acility will operate, to tne extent authorized herein, in confonalty with the application, as amended, the provisions of tne Act, and the regulations of the Coa 91ssion.
A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR Part 50 is described in the Office of liuclear Reactor Regulation's Safety Evaluation deport, Supplement lio. 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 otnerwise 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. Tne facility will operate, to the extent authorized herein, in confonnity with the application as amended, the provisions of tne Act, and the regulations of the Coanission.
E.
The licensee shall maintain in ef fect and fully iuplement all provisions of tne Counissica-approved physical security plan, guard training and qualification plan, and safeguards contingency plan, including amerdments made pursuant to the authority of 10 CFh $50.54(p). The approved plans consist of 10 CFR s2.790(d) information collectively entitled: " Physical Security Plan for th: Sequoyah Nuclear Plant", dated August 25, 1976, as revised on April 2,1979, June 29,1979, September 19, 1979, and December 16,1980; "$eauoyah tiuclear Plant Security Personnel Training and Qualifications Plan" dated August 17, 1979, as revised January 24, 1980, Nay 21,1980, October 1,1980, Marcn 9,1981, and as amended by subsequent approved revisions; and the "Sequoyah liuclear Plant Safeguards Contingency Plan", dated March 1, 1979, as revised Septeuber 1, 1979, April 15, 1980, Deccaber 21,19tio, liarch 30, 1981, and as amended by subsequent approved revisions.
In audition to all other comitments contained in the physical security plan, the licensee shall ensure tnat whenever an employee leaves the employ-ment of TVA, all locks, keys, coabinations, card keys, or related equipment used to control access to the Sequoyah Iduclear Plant protected area or vital areas to which that employee had access shall be changed.
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F.
Reactor Safety tiethodology Applications Programs (Section 24.0)
TVA will provide a report preparea 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 amended license is subject to the following additional condition for the protection of the environ:aent:
Detore engaging in additional construction or operational activities which may result in an environmental impact that was not evaluated by the Com-mission, Tennessee Valley Authority will prepare and record an environ-mental evaluation of such activity. When the evaluation indicates that such activity raay result in a significant adverse environraental impact that was not evi;luated, or that is significantly greater than that evaluated in the Final Environmental Statement prepared by tue Tennessee Valley Authority and tne Environmental Impact Apprsisal prepared by the Commission in llay 1979, the Tennessee Valley Authority sna11 provide a written evaluation of such activities and obtain prior approval from the Director, Office of Huclear Reactor Regulation.
11. TVA shall report any violations of the requirements contained in Sections 2.C(3) through 2.C(16), 2.E, 2.F. and 2.G of tnis 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 tne Regional Office, or his designee, no later than the first working day following the violation with a written followup report within 14 days.
1.
TVA shall imediately not'.fy the Coaaission of any accident at this facility wnich 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 have and maintain financial protection of s.,
type and in such dmounts as the Coraatssion shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
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This aiaended license is effective as of the date of issuance and shall i
expire llay 27, 2010.
FOR TtiE tiUCLLAR Rt.GULATORY ColtilSSI0li i
WW by it.a.s t.
m liarold R. Denton, Director Office of Nuclear Reactor Regulation 4
Attacnments:
1.
Attacho:ent 1 2.
Appendices A and b Technial Specifications Date of Issuance: September 15, 1981 i
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