ML20141K396

Amend 11 to License R-80,modifying Line Organization Which Directs Triga Reactor,In Response to

ML20141K396
Person / Time
Site:	05000157
Issue date:	05/23/1997
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141K393	List: ML20141K388 ML20141K396 ML20141K400
References
R-80-A-011, R-80-A-11, NUDOCS 9705290072
Download: ML20141K396 (14)

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[ 4 UNITED STATES g j NUCLEAR REGULATORY COMMISSION 1

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o, WASHINGTON, D.C. 20666 4001 l

l CORNELL UNIVERSITY TRIGA REACT 0_R DOCKET NO. 50-157 AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No. 11 4

License No. R-80 s

1. The U.S. Nuclear Regulatory Commission (the Comission) has found that:

A. The application filed by Cornell University (the licensee), dated March 7,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Comission as presented in 10 CFR Chapter I;

. B. The facility will operate in conformity with the application, the 1

provisions of the Act, and the rules and regulations of the Commission; j

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 rules and regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of notice for this amendment is not required by 10 CFR 2.106.

9705290072 970523 PDR ADOCK 05000157 P PDR

2. Accordingly, the license is amended by changes to the Technical Specifications as Indicated in the enclosure to this license amendment, and paragraph 2.C.2 of License No. R-80 is hereby amended to read as follows.:

2. The Technical Specification contained in Appendix A, as revised through Amendment No. 11 are herety incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective on the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION "We -

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Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Date of Issuance: May 23, 1997 i

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iXC,LQSilt.TO LICENSE AMENDMENT NO.l?

fA_GI:aTY OPERATING LICENSE NO. R-80 DOCKET NO. 50-157 i

Replace the following pages of the Appendix A Technical Specification with the enclosed pages. The revisid pages are identified by Amendment number and '

contains vertical lines indicating the areas of change.

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Remove Paae Insert Pace 19 19 l 20 20 I

21 21 22 22 l 23 23 24 24 25 25 26 26 j 27 27 28 28 29 l

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6.0 Administrative Controls 1

6.1 Oreanintion and Resnonsibilities of Personnel a ) The TRIGA Reactor located in the J. Carlton Ward, Jr. Laboratory of Nuclear Engineering l shall be an integral part of the Ward Center for Nuclear Sciences of Cornell University.

The reactor organization shall be related to the University structure as shown in Chart I.

b) The Vice President for Research and Advanced Studies shall be responsible for the appointment of responsible and competent persons as members of the Ward Center Safety l

Committee and as Director of Ward Center. In making these appointments he/she shall consult with the Ward Center Advisory Board. l c) The Ward Laboratory (including but not limited to the TRIGA Reactor) shall be under the supervision of the Center Director, who shall have the overall responsibility for safe, efficient, and competent use of its facilities in conformity with all applicable laws, regulations, terms of facility licenses, and provisions of the Ward Center Safety Committee. He/she shall also have responsibility for maintenance and modification of Laboratory facilities. He/she shall have education and/or experience commensurate with the responsibilities of the position. He/she shall report to the Vice President.

d) The Reactor Supervisor shall serve as the deputy of the Center Director in all matters relating to the enforcement of established rules and procedures (but not in matters such as establishment of rules, appointments, and similar administrative functions). He/she should have at least two years of technical training beyond high school and shall possess a Senior Reactor Operator's license. He/she shall have had reactor operating experience and have a demonstrated competence in supervision. He/she shall be appointed by the Center Director with the approveJs of the Vice President and the Ward Center Safety Committee, and shall report to the Center Director.

e) The Responsible Person on Duty shall be responsible for enforcing all applicable rules, procedures, and regulations while he/she is on duty, for ensuring adequate exchange of information between operating personnel when shifts change, and for reporting all malfunctions, accidents, and other potentially hazardous occurrences and situations to the Reactor Supervisor and/or Center Director. Responsible Persons shall possess a Senior '

Operator's license, shall be appointed by the Center Director with the approval of the Center Safety Committee, and shall report to the Reactor Supervisor.

f) The Reactor Operator shall be responsible for the safe and proper operation of the reactor, 19 Amendment No. 11

Cornell University l Board of Trustees 1

President i

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Senier Vice President  :--------------------------------- Provost .

i 1  ? 4 i Vice President University Vice President Facilities and Campus Health and Safety _____ Research and Advanced _ _ _ _ ,

Services Board i Studies a t 1 1 ' '

Ducctor University Ward Center Wani Center  !.

E$ Environmental Health Radiation Safety Safety Committee Advisory Board l g

and Safety Committee l ,, l

/

r-- Ward Center for Nuclear Sciences Director 'a Manager , '

Laboratory and / "

Radiation Safety;

• Ward Center Reactor University RSO Safety Officer Supervisor o

Radiation Safety Staff 4 4 4 Responsible Person Analogouslines for other On Duty,TRIGA areas of Responsibility:

Legend:

Zero Power Reactor Line ofAuthority:  ;

Gamma Cell

• Radioactive Sources and Reactor Operator Line ofAppolnonent Responsibility +: Materials g

Line ofPolicy Responsibility: User Chart I. - Organizational Structure Amendment No.11

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under the direction of the Responsible Person on Dup itcactor Operators shall possess an Operator's or Senior Operator's license and SMI be . ,ppomMd by the Center Director.  !

, g) 'Ihe University Radiation Safety Officer (URSO), or his/her deputy, shall (in addition to l other duties defined by the Director of Environmental Health and Safety) be responsible )

' for overseeing the safety of Ward Center operations from the standpoint of radiation l protection. He/she shall be appointed by the Director of Environmental Health and i Safety with the approval of the University Radiation Safety Committee. He/she shall l report to the Director of Environmental Health and Safety, whose organization is i independent of the Ward Center organization, as shown on Chart I. I h) The Director of Ward Center, with the approval of the Ward Center Safety Committee, may designate an appropriately qualified member of the Center organization as Ward Center Safety Officer (WCSO) with duties including those of an intra-Center Radiation Safety Officer. The University Radiation Safety Officer may at his/her discretion, and

! with the concurrence of the Center Director, authorize the WCSO to perform some of the l l specific duties of the URSO at Ward Center. j l

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l' 6.2 Review and Audit I

a) There will be a Ward Center Safety Committee which shall review TRIGA reactor operations to assure that the reactor facility is operated and used in a manner within the l terms of the facility license and consistent with the safety of the public and of persons l within the Laboratory.

b) The responsibilities of the Committec include, but are not limited to, the following;

1. Review and approval of rules, procedures, and proposed Technical Specifications;

2. Review and approval of all proposed changes in the facility that could have a

! significant effect on safety and of all proposed changes in rules, procedures, and Technical Specifications, in accordance with procedures in Section 6.3;

3. Review and approval of experiments using the reactor in accordance with procedures l

l and criteria in Section 6.4;

! 4. Determination of whether a proposed change, test, or experiment would constitute an

}' unreviewed safety question or change in the Technical Specifications (Ref.10 CFR 2

50.59);

j 5. Review of the operation and operations records of the facility; i 6. Review of abnormal performance of plant equipment and operating anomalies; I -y 7. Review of unusual or abnormal occurrences and incidents which are reportable under 4

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10CFR 20 and 10 CFR 50;

8. Inspection of the facility, review of safety measures, and audit of operations at a frequency not less than once a year; and

• 9. Approval of appointments of Responsible Persons.

c) The Committee shall be composed of:

1. one or more persons proficient in reactor and nuclear physics,  !

2. one or more persons proficient in chemistry or chemical engineering,  !

3. one person proficient in biological effects of radiation,

4. the Center Director, ex officio,

5. the University Radiation Safety Officer or his/her deputy, ex officio, and,

6. a member of the Executive Committee of the Ward Center Advisory Board or his/her deputy, ex officio. ,

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'Ihe same individ ual may serve under more than one category above, but the minimum membership shall be seven. At least five members shall be faculty members. The Reactor Supervisor shall attend and participate in Committee meetings, but shall not be a voting member, l

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d) The Committee shall have a written statement defining its authority and responsibilities, l the subjects within its purview, and other such administrative provisions as are required )

for its effective functioning. Minutes of all meetings and records of all formal actions of the l Committee shall be kept.

1 e) The chairman of the Committee shall be elected by the Committee from its members, except l

that the Center Director shall not serve as chairman. A quorum shall consist of not less than a majority of the full Committee and shall include the chairman or his or her designee.

f) The Committee shall meet a minimum of three times a year.

l 63 Procedures a) Written procedures, revieved and approved by the Ward Center Safety Committee, shall l .be followed for the activities listed below. The procedures shall be adequate to assure the safety of the reactor, persons within the Laboratory, and the public, but should not preclude the use of independent judgment and action should the situation require it. The activities 5- are:

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1. Startup, operation, and shutdown of the reactor, including (a) startup checkout procedures to test the reactor instrumentation and safety systems, area monitors, and continuous air monitors, and (b) shutdown procedures to assure that the reactor is secured before operating personnel go off duty.

2. Installation or removal of fuel elements, control rods, and other core components that significantly affect reactivity or reactor safety.

3. Preventive or corrective maintenance activities which could have a significant effect on the safety of the reactor or personnel.

4. Periodic inspection, testmg or calibration of auxiliary systems or instrumentation that relate to reactor operation.

b) Substantive changes in the above procedures shall be made only with the apprdval of the Center Safety Committee, and shall be issued to the operating personnel in written form.

Temporary changes that do not change the original intent rr ay be made by the Responsible Person on Duty with the concurrence of the Reactor Supervisor or Center Director. If the two parties disagree on the change, the change shall not be made. .'Ihe change and the reasons thereof shall be ncted in the log book, and shall be subsequently reviewed by the Center Safety Committee.

.l c) Determination as to whether a proposed activity in categories (1), (2) and (3) in Section l~ 6.2b above does or does not have a significant safety effect and therefore does or does not l require approved written procedures shall require the concurrence of:

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1. the Center Director, and

2. at least one other member of the Center Safety Committee, to be selected for relevant expertise by the Center Director. If the Director and the Committee memberi;lisagree, or if in their judgment the case warrants it, the proposal shall be submitted to the full Committee, and

3. the University Radiation Safety Officer, or his/her deputy, who may withhold agreement until approval by the University Radiation Safety Committee is obtained, i Determinations that written procedures are not required shall be subsequently r-viewed by the Center Safety Committee. The time at which determinations are made, and the review l and approval of written procedures, if required, are carried out, shall be a reasorable l interval before the proposed activity is to be undertaken.

i d) Determination that a proposed change in the facility does or does not have a significant safety effect and therefor does or does not require review and approval by the full Center i

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I Safety Committee shall be made in the same manner as for proposed activities under (c) above.

6.4 Review of Prooosals for Exoeriments a) All proposals for experiments involving the reactor shall be reviewed with respect to safety in accordance with the procedures in (b) below and on the basis of criteria in (c) below.

b) Procedures:

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1. The experimenter shall describe the proposed experiment in written form in sufficient l detail for consideration of safety aspects. If potentially hazardous operations are 1

involved, proposed procedures and safety measures including protective and monitoring l

equipment shall be described.

2. If the experimenter is a student, approval by his/her research supervisor is required.

if the expenmenter is a staff member, his/her own signature is sufficient.

3. The proposal is then to be submitted to the Center Director for safety review. (In the absence of the Center Director, the Vice President may designate another Center Safety Committee member to act.) Safety approval requires the approval of the Center Director and at least one other person selected by him/her from the membership of <

l the Center Safety Committee. If the two individuals agree, approval is granted. If they disagree, or if in their judgment the case warrants it, the proposal will be referred to the full Center Safety Committee.

4. Review and countersignature by the University Radiation Safety Officer or his/her deputy, who shall, if he/she deems it appropriate, indicate on the form that the l experiment (or portions thereof) cannot be performed except while he/she is present.

5. The scope of the experiment and the procedures and safety measures as described in the approved proposal, including any amendments or conditions added by those reviewing and approving it, shall be binding on the experimr.nter and the operating personnel.

Minor deviations shall be allowed only in the manner described in Section 6.3b above.

6. Transmission to the Reactor Supervisor for scheduling.

c) Criteria that shall be met before approval can be granted shall include:

l- 1. The experiment must fall within the limitations given in Section 3.8.

2. It must not involve violation of any condition of the facility license or of Federal, State, l

University, or Center regulations and procedures. The possibility of an unreviewed safety question (10 CFR 50.59) must be examined.

3. In the safety review the basic criterion is that there shall be no hazard to the reactor, 24 Amen +nent No.11

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! l personnelor public.

4. Each experiment is reviewed with respect to the following factors:

(a) pressure change (b) temperature change '

(c) collapse, implosion, or explosion .

l l (d) change of state of sample during irradiation

! (e) chemical reactions (including corrosion) l

! (f) leakage of radioactive mawrial (double encapsulation is sometimes required)  !

l (g) radiation levels and personnel exposure upon removal of sample l l (h) internal and external radiation hazards to personnel in proposed operations subsequent to sample removal (i) radiation levels in accessible areas during reactor operation (e.g., for beam l

experiments) i (j) adequacy of proposed measures to safeguard against accident during experiment (k) adequacy of proposed emergency procedures (if needed) to supplement standard j emergency procedures in the event of accident l

L (1) number of reactor operations personnel required (m) number and type of radiation monitors required (n) reactivity effects (normal and accidental)

! (o) other relevant factors not included above 1

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5. No explosive material as defined in Title 49, Parts 172 and 173 of the Code of Federal Regulations is permitted within the reactor bay.

I 63 Emernency Plan and Procedures An emergency plan shall be established and followed in accordance with NRC regulations. The plan shall be reviewed and approved by the Center Safety Committee prior to its submission to the NRC. In addition, emergency procedures that have been reviewed and approved by the Center Safety Committee shall be established to cover all foreseeable emergency conditiens potentially hazardous to persons within the Laboratory or to the public, including, but not L limited to, those involving an uxontrolled reactor excursion or an uncontrolled release of l radioactivity. l

. i 6.6 Onerator Recualification i-i I An operator requalification program shall be established and followed in accordance with j NRC regulations.

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6.7 Physical Security Plan A phy>lcal security plan for protection of the re actor plant shall be established and followed in accordance with NRC regulationss 6.8 Action To Be Taken In The Event A Safety Ilmit is Exceeded In the event a safety limit is exceeded a ) The reactor shall be shut down and reactor operation shall not be resumed until authorized by the Director, Division of Reactor Licensing, NRC 1

1 b) An immediate report of the occurrence shall be made to the Chairman of the Center Safety Committee, and reports shall be made to the NRC in accordance with Section 6.11 of these specifications, c) A report shall be made to include an analysis of the causes and extent of possible resultant damage, efficacy of corrective action, and recommendations for measures to prevent or redue the probability of rect vrence. This report shall be submitted to the Center Safety Committee for review, and a suitable similar report submitted to the NRC when authorizatioc to resume o; eration of the reactor is sought.

1 6.9 Action To BeTakea In The E 3ent Of A Reoortable Occurrence a) A reportable occurrence is any of the following conditions: j

1. any actual safety system setting less conservative than specified in Section 2.b, Limiting Safety System Settings;

2. operation in violation of a limiting conditions for operation (Section 3.0);

3. incidents or conditions that prevented or could have prevented the performance of the intended safety functions of an engineered safety feature or the reactor safety system;

4. release of fission products from the fuel;

5. an uncontrolled or unanticipated change in reactivity greater than $0.50;

6. an observed inadequacy in the implementation of either administrative or procedural i controls, such that the inadequacy has caused the existence or development of an unsafe condition in connection with the operation of the reactor;

7. an uncontrolled or unanticipated release of radioactivity.

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Amendment No. 11

i b) In the event of a reportable occurrence, the following actions shall be taken:

1. The reactor shall be shut down at once. The Reactor Supervisor shall be notified and corrective action taken before operations are resumed; the decision to resume shall require approval following the procedures in Section 6.3.

l 2. A report shall be made to include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recunence. This report shall be submitted to the Center Safety Committee for review.

3. A report shall be submitted to the NRC in accordance with Section 6.11 of these specifications.

6.10 Plant Operating Records ~

a ) In addition to the requirements of applicable regulations,in 10 CFR 20 and 50, records and logs shall be prepared and retained for a period of at least 5 years for the following items as a minimum:

l 1. normal plant operation, including power levels;

2. principal maintenance activities;

3. reportable occurrences;

4. equipment and component surveillance activities; j 5. experiments performed with the reactor; l 6. all emergency reactor : crams, including reasons for emergency shutdowns.

l b) The following records shall be maintained for the life of the facility:

! 1. gaseous and liquid radioactive effluents released to the environs; l 2. offsite envimnmental monitoring surveys;

3. fuelinventories and transfers; j 4. facility radiation and contamination surveys; l S. radiation exposures for all personnel;

[ 6. updated, corrected, and as-built drawings of the facility.

6.11 Reoortine Reauirements All written reports shall be sent within the prescribed interval to the United States Nuclear Regulatory Commission, Washington, D.C.,20555, Attn: Document Control Desk, with a copy to 27 Amendment No. 11

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j the Regional Administrator, Region I.

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l In addition to the requirements of applicable regulations, and in no way substituting therefor, I reports shall be made to the US. Nuclear Regulatory Commission (NRC) as follows:

a ) A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the NRC Operation Center and Region I, of;

1. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure;

2. any violation of a safety limit;

3. any reportable occurrences as defined in Section 1.1 of these specifications.

b) A report within 10 days in writing to the NRC Operation Center and Region I ofi

1. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury or exposure; the written report (and, to the extent possible, the preliminary telephone and telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent recurrence of the event;

2. any violation of a safety limit;

3. any reportable occurrence as defined in Section 1.1 of these specifications.

c) A report within 30 days in writing to the Director, Non-Power Reactors and Decommissioning Project Directorate, US. Nuclear Regulatory Commission, Washington, D.C. 20555 of;

1. any significant variation of measured values from a corresponding predicted 6r previously measured value of safety-connected operating characteristics occurring during operation of the reactor;

2. any significant change in the transient or accident analysis as described in the FSR.

d) A report within 60 days after criticality of the reactor in writing to the NRC Operation Center and Region I, resulting from a receipt of a new facility license or an tw adment to i the license authorizing an increase in reactor power level or the installation of a new core, l

describing the measured values of the operating conditions or characteristics of the reactor under the new conditions.

f e) A routine report in writing to the US. Nuclear Regulatory Commission, Document Control l Desk, Washington, DC 20555 and Region I, within 60 days after completion of the first 28 Amendment No. 11

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calendar year of operating and at intervals not to exceed 12 months, thereafter, providing

, the fotlowing inforwtiom 1

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1. a brief na.Tative summary of operating experience (including experiments performed),

changes in facility design, performance characteristics, and operating procedures related to reactor safety occurring during the reporting period; and results of surveillance tests and inspections;

2. a tabulation showing the energy generated by the reactor (in megawatt-hours);

3. the number of emergency shutdowns and inadvertent scrams, including the reasons thereof and corrective action,if any, taken; i

4. discussion of the major maintenance operations psimued during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required;

5. -- a summary of each change to the facility or procedures, tests, and experiments carried i out under the conditions of 10 CFR 50.59;

6. a summary of the nature and amount of radioactive effluents released or discharged to l the environs beyond the effective control of the licensee as measured at or before the point of such release or discharge; 1

7. a description of any environmental surveys performed outside the facility;

l. 8. a summary of radiation exposures received by facility personnel and visitors, including l the dates and time.of significant exposure,and a brief summary of the results of radiation and contamination surveys performed within the facility.

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! Amendment No. 11

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