ML20196J384
| ML20196J384 | |
| Person / Time | |
|---|---|
| Site: | 05000112 |
| Issue date: | 03/08/1988 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196J375 | List: |
| References | |
| R-053-A-012, R-53-A-12, NUDOCS 8803140301 | |
| Download: ML20196J384 (14) | |
Text
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- 'o UNITED STATES
! ~ ,1, NUCLEAR REGULATORY COMMISSION
{ ,$ W ASHINGTON. D. C. 20555
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UNIVERSITY OF OKLAH0t%
DOCKET NO. 50-112 AMENDf1ENT TO FACILITY LICENSE Amendment No. 12 License No. R-53
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment filed by the University of Oklahoma (the licensee), dated October 15, 1987, as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, provisions of the Act, and the regulations of the Comission; .
C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and F. Publication of notice of this amenitent is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
8803140301 880300 PDR ADOCK 05000112 P PDR
- 2. Facility License No. R-53 is hereby amended in its entirety to read as follows:
A. This license applies to the Model AGN-211P, nuclear reactor that is owned by the University of Oklahoma and located on the licensee's campus in Norman, Oklahoma, and described in the licensee's application for license renewal dated October 5, 1978, as supplemented.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the University of Oklahoma:
- 1. Pursuant to Section 104c of the Act and 10 CFR, Chapter I, Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, but not operate, the facility at the designated location in Norman, Oklahoma in accordance with the procedures and limitations described in the application -
and this license;
- 2. Pursuant to the Act and 10 CFR, Chapter I, Part 70, "Domestic Licensing of Special Nuclear Material," to possess, but not to use, up to 1700 grans of contained uranium-235; and
- 3. Pursuant to the Act and 10 CFR, Chapter I, Part 30, "Rules of General Apolicability to Domestic Licensing of Dyproduct Material," to possess, but not to separate such byproduct material as may be produced by operation of the reactor.
C. This license shall be deemed to contain and is subject to the conditions specified in Parts 20, 30, 50, 51, 55, 70 and 73 of 10 CFR, Chapter I, to all applicable provisions of the Act, and to the rules, regulations and orders of the Connission now or hereafter in j effect, and to the additional conditions specified below:
- 1. Operation l
!' The licensee shall not operate the reactor nor install fuel or experiments within the reactor core or core area.
l 2. Technical Specifications i The Technical Specifications contained in Appendix A, as revised through Amendment No. 12, are hereby incorporated in the license.
The licensee shall maintain the facility in accordance with the Technical Specifications.
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- 3. Physical Security Plan The licensee shall maintain and fully implement all provisions of the Comission's approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of a document withheld from public disclosure pursuant to 10 CFR 2.790(d),
entitled "Physical Security Plan, University of Oklahoma, Nuclear Reactor AGN-211P, License No. R-53" (consists of a document dated January 11, 1988 which was submitted by letter dated January 21, 1988).
- 3. This license is effective as of the date of issuance and shall expire at midnight November 14, 2003.
FOR THE NUCLEAR REGULATORY COMMISSION Denn W H.'Crutchfield, D Wector L W. - As Division of Reactor Pro fcts - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Date of Issuance: March 8, 1988 e-m. - -- ,, -e -m - - , . - . --..-m -. - - - _ . . . - - - . _ - .--._-------m r - - _ . --. --....,_ - . _ . , ,
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l APPENDIX A LICENSE NO. R-53 TECHNICAL _ SPECIFICATIONS FOR TIIE UNIVERSITY OF OKLAllOMA REACTOR HODEL AGN-211P (S.N. 102) e F s s 'd
1 TABLE OF CONTENTS PAGE l
1 1.0 DEFINITIONS. . . . . . . . . . . . . . . . . . . . . .
. . . 1 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTING 1
3.0 LIMITING CONDITIONS POR OPERATION. . . . . . . . . . .
2 4.0 SURVEILLANCE REQi'iREMENTS. . . . . . . . . . . . . . .
4.1 Facility dupport and Protection Systea . . . . . . 2
. . . . . . . . . . . . . . . . . . . 3 5.0 DESIGN FEATURES 3
5.1 Mothball Status of the Reactor . . . . . . . . . .
3 5.2 Fuel Storage . . . . . . . . . . . . . . . . . . .
ADMINISTRATIVE CONTROLS. . . . . . . . . . . . . . . .
3.
6.0 3
6.1 Organization . . . . . . . . . . . . . . . . . . .
6.2 Reactor Safety Committee . . . . . . . . . . . . . 5 7
6.3 Reportable Occurrences . . . . . . . . . . . . . .
8 6.4 Procedures . . . . . . . . . . . . . . . . . . . .
9 6.5 Records Retention. . . . . . . . . . . . . . . . .
. . . _ _ , _ _ __ _ _ _______ _._ _ _ . _ _ _ _ . . _ _ _ _ . . _ . _ . . _ . _ ..~. . . _ _ _
1.0 DEFINITIONS 93ta rt erl y. - is defined as 3 months not to exceed 4 months.
Semi-Annual _12 -
is defined as 6 months but not to exceed 7 months.
Annually - Annually is defined as 12 months but not to execed 14 months.
Shut.down Mars.in - The shutdown margin is defined as the amount of negative reactivity by which the reactor is shut down wi th the most reactive rod stuck out of the core.
React or Secured - The reactor shall be considered secured wher .
(1) It centains insufficient fissile material or moderatar .
ptesent in the reactor, adjacent experiments or cor trol
- rocs, to attain criticality under optimum available cotid'.t. ions of moderation and reflection, or (2) ho work is in progr'ess involving core fuel, control rods or control rod drives unless they are physically dem.upl ed f rom the reactor, and (3) The console key switch is in the off position, the key is ren.ov ed from the lock and the reactor consolc has been disconnected from the power supply.
S AFS701: or Mothball - The reactor facility is consider ed to be in L SAFSTOR or mothballed condition when the f acil i t.y 14 '
f r. a s t.a to of protective storage. The facility say be left i t. tac t except that all fissionable materials shall be removed from the reactor pool. The reactor fuel shall be in storage containers located in a fuel storage area. Appropriate surseillance, radiation monitoring, and security procedur es art established under a possession-only licenae to ensure that. the health and safety of the public is not endangered, i
l 2.0 SAFFTY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Not Apr> l i ca bl e . The reactor shall remain secured and t he facility shall be in mothball status.
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3.0 }_1MITING CONDITIONS FOR OPERATION f
l Not Applicable. The reactor shall remain secured and the facility shall be in mothball status.
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4.0 SURVE1LI.ANCE HEQUIREMENTS Actions specified in this section are applicable to the mothballed condition of the facility and shall be performed within the specified surveillance period.
4.1 Fnei,lity Supnort and Protection Systems Apyj i cabi_1 i t y This speci fication applies to the facility support and protect 2on systems such as physical barriers, and radiation motii t.or irig ac ti s i ties .
Q Q ctise T > assun t.h a t. the public health and safety are not er.dar.gered as a r e t.u l t. of physical degradatior. of the faci!i!y dur irig the term of the possession-on!y license .
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- u. ph>>ical bar riers to unauthorized entrance intobuilding,the reat tor fut ili ty and fuel storage area, e.g.,
r.) oms , doors, and access openingn, shall be visually inspect.ed at least once quarterly.
- h. Fuc 1 storage containers and container locking rings s!.a l l be visually inspected at least quarterly.
- e. ? re.d.ation survey of the reactor facility and fuel
- storage area shall be performed at least semi-annually. .
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- d. Radiation surve) instruments shall be calibrated semi-annually.
Pases 1he physical barriers, e.g. building, rooms doors, and access openings are inspected to assure that these barritrn have not deteriorated and that locks and locking apparatus are intact..
Storage contairiers and container locking rings are inspected to assure integrity of the containers. This inspection, in conjunction with the annual fuel inventory and radiation survey of the fuel storage area will verify that radioactive material has not been removed froni the containers or is not.
et.caping or being transported through the containment
! barriers. In addition, the radiation survey provides assurance that radiation doses to facility personnci and to trie public are maintained at a level below 10 CFR 20 lini's.
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e 5.0 DESIGN FEATURES 5.1 Mothbgli a Status of the Reactor l'u r i ng a siothballed stat.e of protective storage:
- a. The reactor fuel is removed from the pool.
- b. All fissionable anterial used in connection with
( operation of the reactor is stored in approved storage containers with k<0.8, containing less than 400 grams of 1:-235 each, and is located in a designated, controlled fuel storage area in accordance with paragraph 5.2 of
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these technical specifications.
5.2 F.m l Florage Fori, it.cludin,: 'f tn-1 devices , shalI be stored in locked r o c .n. ., in the reactor building. The storage array shall be .
such t.) n t U ,77 is nc grenter than 0.8 for all conditions of o.oder,tta on anc reflect.i on.
C.0 ADMINISTR\TTVE CONTRO!E 6." granization of Responsibility for the University cf Ol3thoma Nuclea- Reactor - Administrative control of the reactor is diagrammed in Figure 1.
6.1.1 ligrident - Chief Executive Officer of the University 6.1. 2 l' < vos t - Ct.icf Accden.ic Officer G. : .: M . for Adcis t.i st rati ve Affairs - Chief Administrative Of f i act G . : . 4 i: car _ of Engineerin_g - Administrative Officer in charge of the College of Engineering l..).5 Dtreetor. School of Aerospace. Mechanical and Nuclear EnLineering (AMNE) - The Director is the head of the three degree programs, Aerospace, Mechanical and Nuclear Engineering. The Director will provide proper financial and technical support to ensure the mothball status of tt.e facility is maintained in accordance with all requirements.
6.1.C Reactor Director - Responsible for the general administra-
- t. ion of the facility. In this capacity the Director shall have the authority and responsibility for the facility and, within the limitations set. forth by the facility license, shall make policy decisions nn all matters concerning the safety of the mothball status of the fuel and is advised by the Reactor Safety Committee, the Radiation Safety Comniittee and the University Radiation Safety Of ficer.
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PRESIDENT GM' THE UNIVERSITY OF OKLAHOMA l
l PROVOST l
V. P. FOR ADMINISTRATIVE AFFAIRS I
DEAN OF THE 4
COLLEGE OF ENGINEERING l
DIRECTOR OF THE SCHOOL OF ,
AEROSPACE MECHANICAL AND NUCLEAR ENGINEERING I
PEACTOR REACTOR DIRECTOR RADIATIDN SAFETY COMMITTEE SAFETY OFFICE Fioure 1. Administrative Organization of the DU Reactor.
t se e
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l 6.1.i Reactor Supervisor - Position not needed during t!=e the reactor is in a mothball status.
6.1.8 University Radiation Safety Officer (RSO) - Has over-all responsibility for radiological safety at the University and shall assure that necessary radiation surveys are conducted '
in the Reactor, fuel storage, and other associated labora-tories The Radiation Safety Officer shall review the radio-logical safety aspects of the fuel storage and shall advise the Reactor Director in all matters relative to radiologi-cal safety. The RSO will be a member of the Reactor Safety Committee and the Radiation Safety Committee.
G.1.9 IQp e t.o r Stuf f Qual i fications - The Reactor Director and un>
t em t ur technicians shall meet the minimum qualificat. ions.
set forth in ANS 15.4, "Standards for the Selection and Training of Personnel for Research Reactors." The .
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qualifientions of a certified health physicist shall be accept ab) e.
G.2 R<=cct or Safety Committee -
G.2.'. The Reactor Safet y Committee (RSC) shall be cotoposc3 o:
nct Jess than four members appointed by the Vice-President f or Administrative Af fairs, two of whom wijl be the Radiation Safet> Officer and the Reactor D: ree t.or .
G.L.2. A minimum of fifty percent. (50%. of the membership shell const.itute a quorum. A minimum quorum shall nct be constituted with more than two committee members ~
fron, the operating staff.
(. 2.3. The committee shall have a maximum of three members e
appointed from the reactor operating staff.
6.2.4. Minutes of the meeting shall be taken and subuitted to each member of the committee along with reports presented 1.he committee.
6.2.5. Ad hoe subcommittees may be convened at the request of the chair and will report their findings to the committee.
G.2.6. The chair shall be appointed by the Vice-President for Administrative Affairs. The chair shall be responsible to call the committee into session at least semi-annually and shall make assignments as necessary to the members of the committee. The chair will be respcnsible for the recording of the sinutes and the dissemination of committee reports and minutes. The chair or c:hai 's designate shall have signature authority for the commi t tee. ,
6.2.7. Committee members shall have duties and authority as assigned by the chair.
0.2.8. The committee shall review and approve the consprehensive safety aspects of the fuel storage.
Review and approval by the RSC will include a determination that any previously unreviewed safety question does not pose a hazard to the reactor, reactor personnel, or the environment as defined in 10CFR 50.
Its duties shall include, but not be limited to the following:
A) Review and approve safety standards associated with the mothballed status of the reactor facility which are consistent with the technical specifications of the reactor.
D) Rosiew and approve procedurns as required by the .
technical specification for rearrangement of fuel, surveillance, and security of the fuel.
C) Review and approve proceduren for the modification and/or testing of replacement components assoulated with the radiation monitoring and fuel storage security systems.
D) Review and approve standard procedures for audit and review of the surseillance procedures required by the technicel specifications and security plan.
- f. ) Audit performance at least annually of the reactor staff in the areas facilities manual (proceduren), ,
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maintenance logs and test procedures, surveillaner tests, and physical security plan.
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f l') Review all abnormal occurrences and viointions of
' the technical specifications, evaluating the causes of such events, the corrective action taken and recommending measures to prevent the recurrence of the incident. Report their finding.4 to all authorities as required by the technical specifications and University authority.
6.3 Heporting Reuuirements 6.3.1 Annual Report. An annual report describing the status of the facility, the results of environmental and facility radiation survyes, an evaluation of the performance of security and surveillanen measures, personnel exposures to radiation, and any abnormal occurrences during the previous calendar year shall be submitted to the Director of Nuclear Reactor Regulation prior,to May 31, of each calendar year.
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6.3.2 Repor table Occurrences. Reportable occurrences shall be report ed as expeditiously as possible by telephone and confirmed by telegraph, mailgram or facsimile transmission to the NRC Operations Center (202) 951-0550, no later than the first work day following the event. A written followup report describing the reportable occurrance including causes, probable consequences, corrective actions, and measures to prevent recurrence shall be submitted within 14 days. Information provided shall contain narrative material for a complete explanation of the circumstances surrounding the event. The following events shall be reported:
- a. Discovery of significant, unexplained increase in r.idiation or contamination levels within or around the i e.u t o i- facility or fuel storage area.
- b. N.>r.o r m:. ) degradation discovered in protective barrier >
for the reactor facility or fuel storage area which 5oald compromise the physical security established for*
protective storage of the reactor and reactor fuel.
C.3.3 Snm ial Report s. Special reports which may be required by the Nuclear Regulatory Commission shall be submitted to the Dirr? tor of the appropriate NRC Regional Office within the
- 1. '. n. c per s ed specified for each report.
G.4 Tf r n er;5_u 3 m. There shall be written procedures for the fr,110 ing.
- 1. F.urseillance and testing of equipment and systems reqaired for protective storage of the reactor and
- reactor fue1.
- 2. l'ersonnel radiation protection consistent with 10 CIR 20.
- 3. Accesa contr ol to the reactor facility and fuel and sto: age area.
- 1. Implementation of the security plan.
S. Not.ification of the proper authorities in the event of significant changes in the radiation or contamination levels within the facility.
6.5 Record Het ention 0.5.1 SAFSTOh Records. Retention records or logs relative to the following itemn shall be kept and retained until the license is terminated, unless otherwise specified by the NRC:
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- a. Facility radiation surveys.
- b. Inspections of physical barriers.
- c. Abnormal occurrences,
- d. Environmental Surveys 6.5.2 prior Faellity Oneration Records.
Records or logs relative to the following items sha))
be retained for a period of at least ten years:
- a. Operating logs or data which shall identify:
- 1. Completion of pre-startup checkout, start-up, power changes, and shutdown of the reactor.
- 2. Inst allat. ion or removal of fuel element.s, cor t.rol rods, or experiments that could af f ect. core reactivity.
- 3. Installation or removal of jumpers, special
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tags or notices, or other temporary changes to reactor safety circuitry.
- 4. Rod worth measurements and other reactivity measurements.
- h. l't incipal maintenance operations,
- c. Report.able occurrences.
- d. Surveillance activities required by technical specifications. *
- e. Fucility radiation and contamination surveys.
- f. Experiments performed with the reactor.
- g. Changes 1.o operating procedures.
6.6.3 Other Records Records or logs relatisc to the following items shall be retained for the life of the facility, unless otherwise specified by the NRC:
- a. Gaseous and liquid radioactive effluents released to the environment.
- b. Appropriate off-site environmental monitoring surveys,
- c. Fuel inventories and fuel transfors.
- d. Radiation exposures for all personnel.
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Updated as-built drawings of the facility.
e.
- f. Records of transient or operational cycles for those components designed for a limited number of transients or cycles.
- g. Records o# training and qualifications for members of the facility staff.
- h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- i. Records of meetings of the Reactor Safety Committee.
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